

[FP1.002] Large area beam-generated plasmas for materials processing applications
Robert A. Meger, Richard F. Fernsler, Darrin Leonhardt (Plasma Physics Division, Naval Research Laboratory, Washington, DC 20375-5346), David D. Blackwell, Scott G. Walton (SFA, Inc., Largo, MD 20774)
The Large Area Plasma Processing System (LAPPS) utilizes mA/cm^2, kilovolt electron beams confined by 100-200 gauss magnetic fields to produce large area, low temperature, high density plasmas in a variety of gases.[1] 1 cm thick sheet plasmas of up to 50 x 100 cm have been generated in pulsed and cw systems in proximity to grounded or biased platforms. Negative ion plasmas have also been generated during the beam pulse in attaching gases. A wide range of plasma and particle diagnostics have been fielded and results agree with analytic and particle code predictions. Initial processing tests have been performed on Si and photo-resist etching. Substrate bias voltage and working gas mixture dependencies have been measured. Applications of the technology to large area sputter coating have also been investigated. Progress in experiments and processing tests will be presented.
[1]R.A. Meger, et al, Phys. of Plasmas 8(5), p. 2558 (2001)
[FP1.003] Improved Plasma Isotope Enrichment using Magnetic Mirrors
G. Rosenthal, A. Y. Wong, G. Paskalov, J. Chen (UCLA)
A system of magnetic mirrors is used to improve the
performance of a plasma isotope enrichment device. The
mirror system provides an effective increase in the length
of the device. This allows construction of a smaller device
than previous devices. The magnetic mirrors also provide a
new and improved method of discrimination between resonant
particles and the non-resonant particles. This improved
discrimination results in a higher level of enrichment, or a
higher throughput rate for the device. Dawson and colleges
first demonstrated that ICR heating could be used to enrich
isotopes (Phys Rev Let, 37(23), 1976). The process relies on
the mass dependence of the cyclotron frequency and couples
energy into the cyclotron motion of a resonant ion species.
As the ions drift across a uniform magnetic field region
(0.6 m, 0.8T), the resonant ions gain large amounts of
perpendicular energy. A carefully controlled shallow
magnetic mirror is used to discrimination between the
different ion species, allowing reflection of the resonant
ions. Experiments have been conducted using a number of
different isotopes (O, K, Rb, and Cs). Extensive experiments
have been done with Rb, showing enrichment of Rb-87 from the
natural 27% to over 96% in a single pass, using a small
prototype device with water-cooled copper magnets. Work
supported by DOE.
[FP1.004] Development of RF Plasma Torch at Atmospheric pressure
Sung W. Ahn, Jung G. Kang, H. S. Uhm (Ajou University)
A RF torch operates by feeding helium or argon gas through
two coaxial electrodes that are driven by a 13.56MHz radio
frequency source of power ranging from 40W to 400W. In order
to prevent an arc discharge, a dielectric material such as
quartz is loaded outside of the center electrode that is
connected to the RF power source. The inner surface of the
outer-grounded electrode is also dielectric loaded. A
stable, arc-free discharge was produced at a flow rate of
1.5 l/min of helium gas. Various reactors have been
developed including water grounded electrode. According to
the experimental data, the breakdown voltage varies for
different diameters of inner electrode. An asymmetric
biaxial reactor can ignite plasma at low breakdown voltage,
which is less than that of symmetric coaxial reactor.
However, plasma produced also asymmetrical distribution. The
plasma characteristics are diagnosed, making use of optical
emission spectroscopy (OES). The spectral lines are
monitored according to various conditions of RF plasma
torch. The lines to be analyzed are mostly in the visible
and near infrared regions, and are observed through axial
direction. Experimental results agree reasonably well with
theoretical predictions.
[FP1.005] Reduction of Perfluorocompound Emissions by Microwave Plasma Torch
Yong C. Hong, J. H. Kim, H. S. Uhm (Ajou University)
Surface cleanings are performed within a reduced pressure
chamber by making use of perfluorocompounds (PFC) gases,
which eventually contaminate the atmosphere. These
contaminant gases are emitted with nitrogen gas, which is
used for pump purges. In order to destruct all of the global
warming gases including PFCs, we have developed a plasma
abatement device, an electrodeless microwave plasma torch
operated at the atmosphere pressure. The plasma abatement
device is attached to the vacuum pump, which discharges the
nitrogen gas with contaminants. The abatement was carried
out using oxygen and air as an additive gases. The
destruction and removal efficiency (DRE) of more than 98was achieved for tetrafluoromethane(CF4). The detailed
characterization of CF4 abatement using Fourier Transform
Infrared (FT-IR) and Quadrupole Mass Spectrometer (QMS)
showed the major PFC by-products. Finally, experimental
results indicate that the plasma abatement device for PFC
destruction can be successfully used to abate all of the
global warming gases in the semiconductor industry.
[FP1.006] Synthesis of Iron Nanoparticles in Plasma*
E. Marji, D. McIlroy, R. Padmanabhan, L. Granlund, J. Huso, Y. Kranov, J. Marchinek, C. Ebert, R. Gandy (Physics Department, University of Idaho), M.G. Norton, E. Calvalria (School of Mechanical and Materials Engineering, Wasington State Univ.), B. Justus (Optical Sciences Division, Naval Research Laboratory)
Previous results at Idaho have shown that Carbon-Iron
nanoparticles can be synthesized by a plasma enhanced
chemical vapor deposition process. The nanoparticles can be
then be utilized to fill the channels of nanochannel glass
thus forming a photonic crystal. We have constructed a new
deposition chamber dedicated to understanding the role of
plasma in nanoparticle formation. The channel glass is
mounted on a custom-designed, differentially pumped sample
holder and 10 Torr of differential pressure is applied
across the 5 mm long nanochannels to drive the nanoparticles
through the chanels. Precursor ferrocene ((C5H5)2-Fe) is the
iron and carbon source. We will optimize the synthesis of
these nanoparticles with reference to parameters such as rf
power, background pressure, and sample location. A study of
plasma parameters using Langmiur probes will be undertaken
to measure the plasma temperature and density. Parametric
effects on the synthesis of the particles will be studied. A
Plasma Oscillation Probe (POP)1 will be installed as an
alternative method for plasma characterization. Optimal
nanoparticle growth conditions will be studied. Special
attention will be given to the role of the plasma sheath in
nanoparticle formation. Different plasma sources (rf and DC)
will be compared. 1. Shirakawa and H. Sugai, Jpn. J. Appl.
Phys. 32(1993)5129. *Work supported by Office of Naval
Research and Idaho NSF EPSCoR funding.
[FP1.007] ECR plasma enhanced MOCVD system and the plasma role in film epitaxial growth of GaN and AlN
Yin Xu (1) State Key Laboratory on Materials Modification by Three Beams,2) Department of Electrical Engineering,Dalian University of Technology, Dalian 116024, China), Biao Gu (State Key Laboratory on Materials Modification by Three Beams and Department of Electrical Engineering, Dalian University of Technology, Dalian 116024, China)
Abstract The development of low-dimension structure materials that are very promising for application of electronic device and optoelectronic device depend on the improvement of the technologies of epitaxial growth and characterization. The film growth technology with noninvasive, in situ, real time monitoring is becoming increasingly important as materials structure become more and more complex. A ECR plasma enhanced MOCVD (PEMOCVD) equipment (ESPU-U) with reflection high-energy electron diffraction (RHEED) for the first time has been developed. Multi-cusp Cavity-coupling ECR plasma source was adopted to provide reactive precursors in ESPD-U therefore the growth temperature was decreased and the working pressure was decreased down to the region less than 1Pa,which makes RHEED in situ monitoring possible. In this paper, the structure, key technologies and unique functions of ESPD-U will be introduced systematically. The epitaxial growth of the large lattice mismatch hetero-junction, GaN/ (0001) Al2O3 and AlN/ Al2O3 (0001), by PEMOCVD in the equipment with in situ RHEED monitoring and the important role of plasma in epitaxial growth were investigated. To remove the native oxidation layer producing a fresh substrate surface with atomic level flatness and to establish a template for the epitaxial growth H2(orH2/N2)-plasma cleaning in situ at 550-650¡æ for 2min- 20 min and N2 ¨Cplasma nitriding at 450-550¡æ for 1 min -30min after the cleaning for the surface of (0001) Al2O3 were investigated. Then the epitaxial growth was started by a two-step process including GaN buffer layer growth at low temperature ~500¡æ- 650¡æ for ~20nm and subsequent film growth of GaN and AlN at high temperature ~650¡æ-700¡æ. The films of GaN and AlN were characterized by the RHEED, XRD, AFM. The FWHM of GaN (0002) diffraction peak from 0.5amp;micro;m thick GaN film was 18 min and the FWHM of AlN (0002) diffraction peak from 0.3amp;micro;m thick AlN film was 12 min. The details of the work will be reported at the conference.
[FP1.008] Optimization of Ablation Plasma Ion Implantation
B. Qi, R.M. Gilgenbach, M.C. Jones, M.D. Johnston, Y.Y. Lau, J. Lian, L.M. Wang (University of Michigan, Ann Arbor), G.L. Doll, A. Lazarides (Timken Research, Canton, OH)
A new, optimized configuration for (laser) Ablation Plasma Ion Implantation (APII)[1] has been invented (target perpendicular to substrate), for which we have demonstrated: a) pure ion implantation with minimal contamination, b) elimination of arcing when the bias voltage is applied simultaneously with the laser pulse, c) higher ion dose by a factor of 2, and d) full energy ions by acceleration on only the voltage flattop. A theory of implanted ion current has been developed, with a novel scaling law, which agrees with the experimental results on microsecond time scales.
[1] B. Qi, R.M. Gilgenbach, Y.Y. Lau, M.D. Johnston, J. Lian, L.M. Wang, G. L. Doll and A. Lazarides, APL, 78, 3785 (2001)
Research supported by NSF.
[FP1.009] Platinum Coating on Tungsten Electrodes via Magnetron Sputtering
Saeyoung Ahn, Hong Bae Kim, Hoon Lee (Solco Biomedical Institute, Seoul, Korea), Biophysics Group Collaboration
Various magnetron sputtering techniques are exploited in order to make bio-compatible Pt coating on W and some other metals. The substrate metals are mostly in the 3D shape, and some are cylindrical in the thickness of less than 0.5 mm. Platinum deposits are in the order of 10 to 100 nm. Biased and bipolar sputterings are tried with some microwave power applied. Nonlinear diffusion wave strokes in the surface medium will be discussed.
*Project supported by Ministry of Commerce, Industry, and
Energy, Korea
[FP1.010] Density Gradient Dependent Helicon Modes
Martin Panevsky, Roger Bengtson (Fusion Research Center, University of Texas at Austin)
Radially localized helicon modes have been proposed to provide a fuller description of helicon discharges over a wide span of operating conditions and gas types [1]. These plasma modes could be of vital importance to the VASIMR engine. They depend on a radial density gradient and appear to operate over a range of frequencies inaccessible to traditional helicon discharges. Our work focuses on confirming experimentally the existence and properties of these helicon modes in Argon, Helium, and Hydrogen. We investigate the density profile, power deposition, wavefields, and dispersion relation of the new helicon modes which differ substantially from the properties of the traditional helicon plasma. We are using a set of dual half-turn helical antennas driven at 13.56 MHz. Our diagnostics includes a system for monitoring the plasma impedance, a set of Langmuir probes, a set of magnetic probes, as well as sensors for monitoring the pressure and DC magnetic field.
*Work supported in part by Advanced Space Propulsion Lab, Johnson Space Center, NASA
[1] B. N. Breizman and A. V. Arefiev, Phys. Rev. 84, 3863
(2000)
[FP1.011] MHD Simulation of Magnetic Nozzle Plasma with the NIMROD Code: Applications to the VASIMR Advanced Space Propulsion Concept
Alfonso G. Tarditi, John V. Shebalin (Advanced Space Propulsion Laboratory - NASA Johnson Space Center - Houston, TX (USA))
A simulation study with the NIMROD code [1] is being carried on to investigate the efficiency of the thrust generation process and the properties of the plasma detachment in a magnetic nozzle. In the simulation, hot plasma is injected in the magnetic nozzle, modeled as a 2D, axi-symmetric domain. NIMROD has two-fluid, 3D capabilities but the present runs are being conducted within the MHD, 2D approximation. As the plasma travels through the magnetic field, part of its thermal energy is converted into longitudinal kinetic energy, along the axis of the nozzle. The plasma eventually detaches from the magnetic field at a certain distance from the nozzle throat where the kinetic energy becomes larger than the magnetic energy. Preliminary NIMROD 2D runs have been benchmarked with a particle trajectory code showing satisfactory results [2]. Further testing is here reported with the emphasis on the analysis of the diffusion rate across the field lines and of the overall nozzle efficiency. These simulation runs are specifically designed for obtaining comparisons with laboratory measurements of the VASIMR experiment, by looking at the evolution of the radial plasma density and temperature profiles in the nozzle. VASIMR (Variable Specific Impulse Magnetoplasma Rocket, [3]) is an advanced space propulsion concept currently under experimental development at the Advanced Space Propulsion Laboratory, NASA Johnson Space Center. A plasma (typically ionized Hydrogen or Helium) is generated by a RF (Helicon) discharge and heated by an Ion Cyclotron Resonance Heating antenna. The heated plasma is then guided into a magnetic nozzle to convert the thermal plasma energy into effective thrust. The VASIMR system has no electrodes and a solenoidal magnetic field produced by an asymmetric mirror configuration ensures magnetic insulation of the plasma from the material surfaces. By powering the plasma source and the heating antenna at different levels it is possible to vary smoothly of the thrust-to-specific impulse ratio while maintaining maximum power utilization.
[1] http://www.nimrodteam.org [2] A. V. Ilin et al., Proc.
40th AIAA Aerospace Sciences Meeting, Reno, NV, Jan. 2002
[3] F. R. Chang-Diaz, Scientific American, p. 90, Nov. 2000
[FP1.012] Scaling of the VASIMR thruster first stage operation
Kim Molvig (MIT, Cambridge, MA 02139, USA), Oleg Batishchev (MIT, USA /MIPT, Russia)
An effective helicon plasma source [1,2] is used in the variable high specific impulse VASIMR plasma thruster [3]. Experimental prototypes – VX-3 and recently up-scaled VX-10 [4] configurations operate with hydrogen, deuterium and helium plasmas. A set of models [5-7] has been developed to study VASIMR light gases helicon discharge. Using zero-dimensional model incorporating energy and mass balance equations we study scaling of the plasma source efficiency with the increased mass flow rate, applied electrical power and dimensions of the quartz tube. We compare theoretical results with existing experimental data.
[1] M.A.Lieberman, A.J.Lihtenberg, 'Principles of ..', Wiley, 1994; [2] F.F.Chen, Plas. Phys. Contr. Fus. 33, 339, 1991; [3] F.Chang-Diaz et al, Bull. APS 45 (7) 129, 2000; [4] J.Squire et al., Bull. APS 45 (7) 130, 2000; [5] O.Batishchev, K.Molvig, AIAA technical paper 2000-3754, 2001; [6] O.Batishchev, K.Molvig, IEPC-01-208 paper, 27th Int. Electrical Propulsion Conf., 2001; [7] O.Batishchev, K.Molvig, AIAA technical paper 2002-0347, 2002.
[FP1.013] Study of electron and ion transport in a Hall effect thruster
Manuel Martinez-Sanchez (MIT, Cambridge, MA 02139, USA), Oleg Batishchev (MIT, USA /MIPT, Russia)
Plasma transport in the Hall effect thrusters was a subject of many studies [1-2]. Despite this fact, the origin of a so-called anomalous transport is not understood to this date. Therefore, theoretical and numerical models [3-4] assume ad-hoc cross-field diffusion coefficients, which may differ by several times from the classical Bohm result. To study the transport phenomenon we have developed several models. One of the models is 2-dimensional in space (for axial and azimuthal directions), and 3-dimensional in velocity. A similar geometry was adopted in works [5], but we try to push the simulation to the realistic scale (several centimeters), while keeping the minimum spatial resolution on the order of the Debye length. It is hoped that the numerical results will provide a better understanding of the anomalous transport in Hall thrusters due to the collective modes.
[1] M.Hirakawa, IEPC-97-021 technical paper, 1997; [2] V. I. Baranov et al., IEPC-95-44, Moscow, 1995; [3] J.Szabo et al, IEPC-01-341, Pasadena, 2001; [4] V.Blateau et al, AIAA technical paper 2002-4105, 2002; [5] M.Hirakawa and Y.Arakawa, IEPC-95-164 technical paper, 1995; AIAA-96-3195 technical paper, 1996.
[FP1.014] Control of plasma flow in Hall thruster with active and passive segmented electrodes
Yevgeny Raitses, David Staack (Princeton Plasma Physics Laboratory), Michael Keidar (University of Michigan, Ann Arbor), Alexander Dunaevsky, Nathaniel Fisch (Princeton Plasma Physics Laboratory)
Segmented electrodes, made from metal or ceramic spacers and having sizes comparable to, but smaller than, the acceleration region in Hall thrusters, are shown to significantly affect the plasma potential distribution. Associated with the potential changes are changes in the electron temperature and electron transport. We show that these changes are connected to changes in the physical properties of the electrodes, such as secondary electron emission and conductivity. The plasma potential distribution depends also on the operating conditions of the thruster, as well as the geometry and precise placement of the electrodes relative to the magnetic field distribution. These results can be explained, in part, through a hydrodynamic description of the thruster.
This work was supported by the New Jersey State Commission
on Science and Technology and by the US DOE under Contract
No. DE-AC02-76CHO3073.
[FP1.015] ENHANCED IONIZATION IN THE CYLINDRICAL HALL THRUSTER
A. Smirnov, Y. Raitses, N.J. Fisch (Princeton Plasma Physics Laboratory)
Conventional annular Hall thrusters do not scale efficiently to low power. An alternative approach, a 2.6 cm miniaturized cylindrical Hall thruster with a cusp-type magnetic field distribution, was developed and studied. Its performance was compared to that of a conventional annular thruster of the same dimensions. The cylindrical thruster exhibits discharge characteristics similar to those of the annular thruster but has much higher propellant ionization efficiency. Significantly, a large fraction of multicharged xenon ions might be present in the outgoing ion flux generated by the cylindrical thruster. The operation of the cylindrical thruster is quieter than that of the annular thruster. The characteristic peak in the discharge current fluctuation spectrum at 50-60 kHz appears to be due to ionization instabilities. In the power range 50-300 W, the cylindrical and annular thrusters have comparable efficiencies (h=15-32configuration, the voltage less than 200 V was not sufficient to sustain the discharge at low propellant flow rates. The cylindrical thruster can operate at voltages lower than 200V, which suggests that a cylindrical thruster might be designed to operate at even smaller power.
This work was supported by grants of AFOSR and DARPA
[FP1.016] Anode Sheath in Hall Thrusters
Leonid Dorf, Yevgeny Raitses, Nathaniel Fisch (Princeton Plasma Physics Laboratory, Princeton, NJ), Vladimir Semenov (Institute of Applied Physics, Nizhny Novgorod, Russia)
Steady-state operation of a Hall Thruster at moderate
discharge voltages requires the presence of a negative anode
sheath and a back-ion flow in order to limit the electron
flux towards the anode. An increase of the discharge voltage
leads to the increase of the discharge current; however, the
electron temperature is limited by the secondary electron
emission from the channel walls. Therefore at large
discharge voltages the electron drift velocity at the anode
may become on the order of or larger than the electron
thermal velocity, rendering the sheath unnecessary or making
it positive. A quasi one-dimensional steady-state model of
the Hall thruster with a given temperature profile shows
that the applied discharge voltage determines the operating
regime: for discharge voltages greater than a certain value,
the negative anode sheath and the back-ion flow disappear.
Both “no sheath” and “positive sheath” regimes may be
responsible for limitations on outgoing jet velocity and
accelerating efficiency observed experimentally for Hall
thrusters operated at high discharge voltages. This work was
supported by the US DOE under contract No.
DE-AC02-76CH03073.
[FP1.017] High frequency instabilities in Hall thrusters
Andrei Litvak (Archimedes Technology Group, Inc.), Yevgeny Raitses, Nathaniel Fisch (Princeton Plasma Physics Laboratory)
Gradient-driven Rayleigh-type instabilities in Hall plasma
thrusters were analyzed using linearized two-fluid
hydrodynamic equations. Necessary instability conditions and
a general criterion for stability of azimuthally propagating
perturbations were derived. For a simplified model of the
axial distribution of parameters inside the thruster
channel, the growth rate of an unstable wave, resonant with
the azimuthal electron flow, was obtained. To study
experimentally the high-frequency (1-100MHz) phenomena in
Hall thruster plasma a novel diagnostic setup, consisting of
single Langmuir probe, special shielded probe
connector-positioner, and electronic impedance-matching
circuit, was successfully built and calibrated. Through
simultaneous probing of the Hall thruster plasma at multiple
locations, azimuthal high-frequency waves have been
successfully identified and characterized. The frequency and
phase relations of the detected waves are in good
qualitative agreement with the theoretical predictions for
the Rayleigh-type instability.
[FP1.018] Modeling Electron Transport in Two Dimensional Simulations of Hall Thrusters
Eduardo Fernandez (Eckerd College), Mark Cappelli (Stanford University)
A two dimensional (r,z) hybrid (fluid electrons, PIC ions
and neutrals) code has been written in order to understand
Hall thruster dynamics. At issue is the role played by the
electron transport in these discharges. Previous simulations
have used various models for the electron conductivity, from
collisional or "classical" to Bohm. Experimentally, it has
been observed that such conductivity is a complex function
of axial distance. At high voltage, the electron transport
is reduced (as compared to the Bohm estimate) in the
acceleration region where the azimuthal electron flow is
strongly sheared, concomitant with a reduction of the
relative level of fluctuations. In our simulations, we use
an empirical model for the conductivity based on these
observations and apply it to two thruster geometries. The
results are then compared with previous simulations.
[FP1.019] The effects of ionization and catalytic recombination on Hall discharge stability
Nathan Meezan, Nicolas Gascon, Mark Cappelli (Stanford University Department of Mechanical Engineering)
Coaxial Hall-effect accelerators are low-pressure,
cross-field discharges which are primarily used as highly
efficient ion rockets. Hall discharges exhibit rich
oscillatory behavior that is thought to be important to
enhanced cross-field electron transport. This study expands
a two-fluid, four-equation linear stability analysis
performed by Morozov in 1972 (\emphZhurnal Tekhnicheskoi
Fiziki \textbf42, 612-19) to include new physical
effects. In the original analysis, local stability is
dictated by gradients in the plasma density and magnetic
field. Including a source/sink term to account for
ionization and recombination changes the stability limits
such that the discharge is unconditionally unstable. When
the plasma is primarily recombining, oscillations are
strongly damped at most angles of propagation. Since
electron loss is dominated by catalytic recombination at the
channel wall, this damping couples the plasma oscillations
to the electron-wall interaction in the discharge. Results
of the stability analysis are compared qualitatively to
recent experimental investigations of a laboratory Hall
discharge with alumina walls.
[FP1.020] Characterization of ionization instabilities in a Hall-effect accelerator
Nicolas Gascon, Nathan Meezan, Mark Cappelli (Stanford University, Mechanical Engineering Department)
Hall-effect accelerators are low-pressure, cross-field
discharges, which are primarily used as highly efficient ion
rockets. Many aspects of the electron dynamics within the
discharge of such an accelerator remain to be clarified, and
in particular the role that instabilities and plasma-wall
interactions can play in the diffusion towards the anode.
The dispersion properties of low-frequency (below 200kHz)
waves in a Hall-effect annular ion accelerator are
presented. Two types of materials with different secondary
electron emission properties were used as the discharge
chamber wall: boron nitride and alumina. The discharge was
operated mainly in the ionization branch of the
current-voltage characteristic . Fluctuations in the
discharge current and of the plasma density were
simultaneously recorded, at three different positions, by
electrostatic probes negatively biased to the ion current
saturation branch. The general features and possible origin
of the observed instabilities are discussed.
[FP1.021] Hall Thruster Plume Studies using the BeamServer Antenna Pattern Code
G.A. Hallock, J.C. Wiley, A. Garcia, C. Zuniga, A. Boulgakov (The University of Texas at Austin), J.W. Meyer, J.T. Loane (Lockheed Martin Space Systems Corp.)
BeamServer is a ray tracing code developed to study the
effect of plasma thruster plumes on satellite communication
signals. Rays are launched from the antenna feed, traced
through the region containing antenna reflectors and plasma,
and terminated on an exit surface. The electric field on the
exit surface is then used to calculate the far-field antenna
pattern, using the radiation integral. To verify both the
code operation and our thruster plasma density models a
"ground test" is planned, where a Hall thruster will be
operated in a vacuum tank and a microwave system will
transmit through the plume. Direct comparisons with ground
test experimental data can be made on the BeamServer exit
plane. To facilitate this extensive studies of the electric
field magnitude and phase as a function of frequency and
spatial location have been made. In addition, the Hall
thruster exhibits large amplitude plasma instabilities,
typically in the 25 KHz range. We have added instability
models to the BeamServer code, and added time as a variable.
Fourier transforms can be applied to either the exit plane
or far-field patterns. We will present these studies and
discuss the planned ground test.
[FP1.022] Hall Thruster Impact Analysis on Digital Satellite Communications
C. D. Zuniga, G. A. Hallock, J. C. Wiley (The Univ. of Texas Austin,TX), J. W. Meyer, J.T. Loane (Lockheed Martin Space Systems Co. Sunnyvale,CA)
Hall Thrusters will be used for stationkeeping of geosynchronous communications satellites. These thrusters produce an inhomogeneous plasma plume which may interfere with communications signals (1-20 GHz) to and from the satellite. The plume's effects include beam-pointing error, beam attenuation, and spectral modulation [1]. Many systems digitally modulate an RF carrier and use coherent detection methods. The plasma may degrade the performance of these systems by diminishing the SNR at the receiver by squinting the beam away and degrading the synchronization by phase modulating the signal. We simulate a receiver whose input signals have been corrupted by the plasma plume. These modified input signals are formed by using the results of a previously developed ray tracing code [1]. We will present performance measures including bit-error rates and link availability.
* Work supported by Lockheed Martin Corp. and the Texas Higher Education Coordinating Board.
[1] Hallock et al, J. Spacecraft and Rockets V. 39 No 1 pp
115-124
[FP1.023] Ion Drift and Ion Temperature in the MNX Nozzle Region
Robert Boivin (Department of Physics, Auburn University, AL 36849-5311), Amy Keesee, Earl Scime (Department of Physics, West Virginia University, WV 26506-6315), Sam Cohen (Princeton Plasma Laboratory, Princeton, NJ 08543)
A novel diode laser based LIF diagnostic is used to measure
argon ion drift velocity and ion temperature near the nozzle
of the MNX (Magnetic Nozzle Experiment) device. The laser is
injected along the magnetic field axis and the fluorescence
of both Zeeman sigma components are detected. The
fluorescence linewidth is a convolution resulting from
mostly Doppler and Zeeman broadenings. By using a
de-convolution technique, the resulting fluorescence signal
yields both the ion temperature and the ion drift. Ion
temperatures in the nozzle region are within the 0.05 to
0.25 eV range, which is comparable to what was observed in
the MNX inner plasmas. Preliminary result suggests that,
under specific plasma conditions, drifting ion populations
are present within (or beside) the thermal ion
distributions. Specifically, LIF measurements near the
nozzle (10 cm) reveal the presence of a hot tail within the
ion distribution function. Further away from the nozzle (22
cm) two ion distributions of comparable intensities are
observed. The first one is unshifted and thus stationary,
while the second is moving away from the nozzle with a 4 eV
(6.5 GHz) drift. The relative intensity of the drifting
distribution is important when the pressure near the nozzle
remains low but quickly diminish with increasing pressure.
The magnitude of the drift also significantly decreases with
raising pressure. Colder ions (0.05 eV) are commonly
observed under high pressure conditions.
[FP1.024] Plasma Source and Equatorial Characteristic Dependencies of The Mini-Magnetospheric Plasma Propulsion (M2P2) Prototype during Large Chamber Experiments
T. Ziemba (Aeronautics and Astronautics, University of Washington), R. Winglee (Earth and Space Sciences, University of Washington), J. Slough (Aeronautics and Astronautics, University of Washington), P. Euripides (Earth and Space Sciences, University of Washington), L. Giersch (Aeronautics and Astronautics, University of Washington)
Magnetospheric Plasma Propulsion (M2P2) seeks the creation
of a magnetic wall or bubble (i.e. a magnetosphere) that
will intercept the solar wind and thereby provide high-speed
propulsion with efficient propellant utilization and power
requirements. For successful inflation of the magnetic
bubble a beta of unity must be achieved along the imposed
dipole field. This is dependent on the plasma parameters
that can be achieved with plasma sources that provide
continuous operation at the desired power levels.
Investigations of a 1.5 cm radius Helicon plasma source to
generate plasma along an imposed dipole magnetic field have
been conducted in a new 3800 liter vacuum chamber at the
University of Washington. Steady state plasma generation has
been accomplished while maintaining a very low neutral gas
pressure (< 10-5 Torr) in the chamber allowing for
magnetized plasma to be inserted along the dipole field.
Measurements of plasma characteristics have been made using
swept asymmetric double Langmuir probes for several
different experimental configurations. Results show a
building of plasma density in the outer equatorial region of
the dipole with a peaked profile that is highly dependent on
source and dipole magnet geometry.
[FP1.025] Data Voltage Effects on Sustaining Discharge and its Implication on Luminescence in Plasma Display Panels
C. G. Ryu, Y. Jung, E. H. Choi, T. S. Cho, J. H. Choi (Kwangwoon University), H. S. Uhm (Ajou University)
The sustain discharge in widely used AC-PDP cells with a
three electrode system occurs in the space between the
parallel-sustain electrodes of X and Y on the front glass
plate. But the wall charge is formed on the dielectric layer
covering the X and Y electrodes, and also formed on the
dielectric layer over the address electrode Z on the rear
glass plate. Data voltage is applied to the address
electrode. The luminescence of the plasma display panel
(PDP) under a certain wall charge configuration decreases,
because the wall charge prevents the normal sustaining
discharge. The wall charge accumulation on the rear glass
plate can be experimentally adjusted by applying the data
voltage to the address electrode during the sustaining
discharge period. Influence of the data voltage on the
discharge characteristics in cells of AC-PDP and on the
luminescence of the surface discharge is investigated. It is
found from experimental observation that the wall charge on
the rear dielectric layer is not formed, whenever the
applied data voltage during the sustaining discharge is
40~60 achieving the highest luminescence in AC-PDP.
[FP1.026] Measurement of Electron Temperature and Density in AC Plasma Display Panels
I. R. Cho, M. W. Moon, C. G. Ryu, M. C. Choi, E. H. Choi (Kwangwoon University), H. S. Uhm (Ajou University)
The present AC-PDP has several technical problems, including
low brightness and low efficiency. In order to overcome
these difficulties, it is necessary to find the fundamental
properties of the plasmas generated from the electrical
discharge in PDP cells. For the investigation of the basic
parameters in AC-PDP plasma, the micro Langmuir probe and
ICCD (Intensified Charge Coupled Device) camera have been
used to diagnose electron temperature and plasma density in
AC-PDP cells. It is observed from the experiment that the
electron temperature, obtained from both the micro Langmuir
probe and high speed camera, decreases from 1.8 eV to 0.9 eV
as the pressure of the neon gas increases from 150 Torr to
350 Torr. It is noted that the measured electron
temperatures from the Langmuir probe and high speed camera
are in good agreement with each other within a 5£¥ error
margin. The plasma density at the lateral distance of 125 §
from the center of the sustaining electrode gap has been
found to decrease from 3.7 ¢¥ 1011 cm-3 to 2.3 ¢¥ 1011 cm-3,
as the gas pressure increases from 150 Torr to 350 Torr.
[FP1.027] MST and Reversed Field Pinch
[FP1.028] MST Progress and Plans
J.S. Sarff (University of Wisconsin-Madison), for the MST Team
New diagnostic capability combined with turbulence control
is producing a clearer picture of magnetic
fluctuation-induced transport. Local stochastic transport
depends on both the mode amplitudes and the density of
nearby resonant surfaces. Radially resolved measurements of
the electron heat diffusivity agree with theoretical
estimates \sim v_th(b/B)^2, but only where the
resonant surface density is high. With auxiliary current
drive, broadband mode suppression reduces the local
transport to create RFP global confinement comparable to
tokamak plasmas. In this case an increased population of
high energy electrons (inferred from hard x-ray emission) is
inconsistent with the velocity dependence characteristic of
stochastic diffusion. This plus direct measurement of
reduced fluctuations in the core by FIR polarimetry evidence
closed magnetic surface formation. Core electrostatic
fluctuations are also measured with a heavy ion beam probe
for the first time in an RFP. The nonlinear evolution of the
magnetic spectrum is studied using bi-spectral techniques,
and, for the first time, m=0 modes are measured to be
linearly stable (in standard RFP plasmas). An oscillating
BT, applied to test ac helicity injection, entrains sawtooth
magnetic relaxation processes. Ion temperature profiles are
obtained using CHERS and Rutherford scattering. For future
plasma control, a 2nd generation lower hybrid antenna shows
improved performance, and electron Bernstein wave coupling
is high in improved confinement plasmas, self-consistent
with profile control requirements. Also, a new pellet
injector provides core fueling. Work supported by US DOE.
[FP1.029] Dynamics of Perpendicular and Parallel Plasma Momenta in the MST Reversed Field Pinch
G. Fiksel, A.F. Almagri, D. Craig, D.J. Den Hartog, C.C. Hegna (Department of Physics, Universify of Wisconsin-Madison)
The dynamics of the perpendicular plasma momentum and
parallel plasma momentum over sawtooth crashes and
associated magnetic reconnections is studied in the core and
at the edge of reversed field pinch plasmas. Both the
parallel and perpendicular plasma velocities exhibit sudden
changes during the reconnections. The core plasma velocity
is measured with Doppler spectroscopy and the edge velocity
is measured with a Mach probe. The study reveals that the
plasma parallel momentum relaxes over the plasma radius
similar to the current profile relaxation predicted by
Taylor's theory and experimentally observed in MST. The
flattening of the parallel plasma momentum profile is in
good agreement with the theoretical predictions of two-fluid
MHD. Local measurements of the j\timesB plasma
torque associated with magnetic fluctuations are done at the
plasma edge with an insertable magnetic probe. The
measurements indicate that the torque is much higher than
the rate of change of the corresponding plasma momentum.
[FP1.030] Tokamak-like energy confinement with high beta in the MST RFP
B.E. Chapman, A.F. Almagri, J.K. Anderson, T.M. Biewer, P.K. Chattopadhyay, D. Craig, D.J. Den Hartog, G. Fiksel, C.B. Forest, R. O'Connell, S.C. Prager, J.C. Reardon, J.S. Sarff, M.D. Wyman (UW-Madison), D.L. Brower, W.X. Ding, S.D. Terry (UCLA)
Recent improvements in magnetic fluctuation control in the
MST have led to a 10-fold increase in the energy confinement
time, which reaches 10 ms. Concurrently, beta-total exceeds
15 percent, and beta-poloidal exceeds 18 percent. In
addition to exceeding for the first time the historical RFP
constant-beta confinement scaling, the 10 ms confinement
time also falls within a factor of two of the predictions
from the tokamak (ITER) L-mode and ELMing-H-mode scaling
laws. The proximity of MST confinement to tokamak-scaling
predictions may not be coincidental. High-energy runaway
electrons up to 100 keV are for the first time confined in
the MST plasma core, and diffusion of these electrons is
independent of their velocity. This suggests a transition
from the usual stochastic magnetic field to well-formed
magnetic flux surfaces and that core transport may now be
dominated not by magnetic fluctuations, but by electrostatic
fluctuations instead. Work supported by USDOE.
[FP1.031] Hard X-ray Diagnosis of the Fast Electron Distribution in the MST RFP
D. J. Den Hartog, C. B. Forest, R. O'Connell (University of Wisconsin-Madison), R. W. Harvey (CompX)
Hard x-rays (5-100 keV) are recorded in MST only during
improved confinement discharges produced by inductive
current profile control. The emergence of hard x-rays
indicates good confinement of runaway electrons in an RFP.
Fokker-Planck modeling of the x-ray emission shows fast
electron diffusion is small and independent of energy,
evidence that transport is no longer dominated by magnetic
fluctuations during the improved confinement period. The
hard x-ray diagnostic has recently been upgraded to a
16-channel CdZnTe array. Rather than using conventional
pulse height analysis, the shaped output pulses from each
detector are directly digitized. This cost-effective
technique allows for excellent energy resolution, dynamic
time binning, and better noise rejection/pile-up detection.
This array will enable profile measurements of fast electron
production and transport, and will provide critical
diagnostic support to RF current drive experiments on MST.
[FP1.032] Ion Temperatures and Magnetic Fluctuations in the Madison Symmetric Torus in Steady-State
J.C. Reardon, B.E. Chapman, D. Craig, G. Fiksel, S.C. Prager (University of Wisconsin--Madison), and the MST Team
Previous work (Scime et al., Phys Fluids B \textbf4 (12),
4062) has established a link between ion heating and
magnetic fluctuations on MST during a Magnetic Reconnection
Event (MRE). Here we report on observations in the
steady-state, more than 0.2 ms before or after and MRE. In
standard MST discharges, the steady-state ratio
T_i/T_e > 0.5. This T_i is too large to be
explained by a balance between classical collisional heating
by electrons (P_ei) and charge exchange loss (P_CX).
In MST discharges with Pulsed-Poloidal Current Drive (PPCD),
magnetic fluctuations drop significantly, T_e increases
by a factor of 2, P_ei increases by a factor of 5, the
global energy confinement time \tau _e increases by a
factor of at least 5, and P_CX decreases by a factor of
2. Nonetheless, as a result, T_i increases by only about
20% when compared to standard discharges, and can be
explained by a balance between P_ei and P_CX.
Magnetic fluctuations are measured by coils and flux loops
in the plasma edge. The temperature of the bulk majority ion
species is measured by Rutherford Scattering, while the
temperature of fully-stripped impurity species is measured
by CHERS; these temperatures are found to be equal. Work
supported by US DOE.
[FP1.033] Modeling and measurements of magnetic stochasticity and transport in the MST reversed field pinch
Ben Hudson (UW - Madison), J.K. Anderson, T.M. Biewer, G. Fiksel, S.C. Prager, J.S. Sarff, MST Group, Y. Tsidulko
Results from experimental measurements and modeling of stochastic transport are beginning to agree. The modeling was done with a field line tracing code, which uses spatial profiles from a 3-D nonlinear MHD code, DEBS, and incorporates experimentally measured edge fluctuations. The modeling finds good agreement with Rechester - Rosenbluth diffusion just inside the reversal surface, where the islands highly overlap, and diverges from Rechester - Rosenbluth elsewhere. Electron heat transport is measured experimentally and agrees with the model to within a factor of three. Measurements of the drop in electron thermal transport in plasmas where fluctuations are suppressed by current profile manipulation are in agreement with the model. Recent measurements of the confinement of run-away electrons observed in the core suggest reformation of magnetic flux surfaces from a previously stochastic field. The modeling clearly shows this transition in profiles of radial magnetic field line diffusion. In addition we have started modeling of fast ion motion and new results on the effect of magnetic field stochasticity on the ion confinement will be reported.
Work supported by U.S. D.O.E.
[FP1.034] Electron Bernstein Wave Heating in the Madison Symmetric Torus Reversed Field Pinch
J. K. Anderson, M. Cengher, P. K. Chattopadhyay, C. B. Forest, R. O'Connell (University of Wisconsin), R. I. Pinsker (General Atomics), M. D. Carter (Oak Ridge National Laboratory)
A system to heat electrons in the Madison Symmetric Torus
through the electron Bernstein wave is currently being
developed. This is an attractive heating scheme for the
overdense RFP plasma, where electron cyclotron heating and
current drive are inaccessible. Low power experiments
(\sim 1 watt) have shown that a significant fraction of
launched electromagnetic power successfully couples to the
electron Bernstein wave. Furthermore, these experiments have
found an optimized launch with finite N_\perp. We present
the initial results from a moderate power (\sim 150 kW),
several millisecond experiment driven by a pair of S-band
traveling wave tube amplifiers. Electromagnetic power will
be injected into plasmas with similar Ohmic heating levels
(200 - 300 kW), and the effects on the electron distribution
will be monitored with x-ray detectors. This work is
supported by USDOE.
[FP1.035] EBW Coupling Experiment in Overdense RFP Plasma
P.K. CHATTOPADHYAY, J.K. ANDERSON, M. CENGHER, C.B. FOREST, V. SVIDZINSKI (University of Wisconsin Madison), R.I. PINSKER (General Atomics, San Diago), M.D. CARTER (ORNL, Oak Ridge)
Experimental observation of blackbody emission from MST
establish the viability of EBW heating in over-dense
plasmas. However, a major technical challenge is to develop
a robust technique for coupling high power to the EBW from
external antennas. Our experimental results show the
possiblities to couple energy to the EBW in RFP geometries.
The antenna, two S-band waveguide with one common E-plane
wall, launches wave with a finite N_\perp with an
externally imposed phase shift between the waves in each
waveguide. Power from a single TWT amplifier ( < 10 watts)
at 3.6 GHz was divided and fed into two arms of twin
waveguide through isolators and bidirectional couplers. A
mechanical phase shifter was used to manually vary the
interwaveguide phase between plasma shots. The amplitudes
and phases of the forward and reflected powers were measured
for each waveguide. Vacuum measurements agree well with
theory. Coupling has also been measured in PPCD plasmas.
During PPCD a substantial reduction (from 80% to 20%) in
the reflected power was observed. The asymmetry in coupling
with respect to N_\perp is clearly observed in
measurements.
[FP1.036] Coupling to the Electron Bernstein Wave With Wave- guide Antennas: Theory and Experimental Results from MST
R.I. Pinsker (GA), M.D. Carter (ORNL), C.B. Forest, P.K. Chattopadhyay, M. Cengher, V. Svidzinski (U.\ Wisconsin-Madison)
The electron Bernstein wave (EBW) is of interest for both diagnostic applications and for heating and current drive in low field devices such as present spherical torus experiments and the reversed-field pinch (RFP). In these devices, neither X- or O-modes can propagate in the interior of the plasma. We compare the predictions of a generalized waveguide coupling code~[1] to the experimental results from the MST RFP in which a pair of S-band waveguides were oriented to excite the X-mode (which couples to the EBW near the upper hybrid resonance) in the edge of the plasma. Good qualitative agreement between the predicted phase dependence of the reflection coefficient and the measured results is obtained. In particular, the predicted strong dependence of the coupling on the sign of the toroidal phasing was observed.\par \vskip3pt [1]~Pinsker, R.I., et al., in Radio Frequency Power in Plasmas (Proc.\ 14th Top.\ Conf., Oxnard, CA, 2001), (AIP, Melville, NY, 2001) p.~350.
[FP1.037] Interdigital Line Antennas for Launching LH Waves in MST
M.A. Thomas, J.A. Goetz, S.P. Oliva (University of Wisconsin-Madison)
RF current drive has been proposed as a method for reducing the tearing fluctuations that are responsible for anomalous energy transport in the RFP. A system for launching lower hybrid slow waves at 800 MHz and n_||= 7.5 is now in operation on MST. The antenna is an enclosed interdigital line using \lambda/4 resonators with an opening in the cavity through which the wave is coupled to the plasma. A new antenna has been built incorporating several design improvements. These include larger vacuum feedthroughs, better impedance matching, internal instrumentation and improved directionality. Power handling is 3-4 times that of the original and continues to improve with conditioning. Further design improvements are underway to optimize impedance matching and damping rate along the traveling wave structure.
[FP1.038] Lower Hybrid Experiments in MST
J. A. Goetz, M.A. Thomas, P.K. Chattopadhyay, R. O'Connell, S.P. Oliva, P.J. Weix (University of Wisconsin - Madison)
Current drive using RF waves has been proposed as a means to
reduce the tearing fluctuations responsible for anomalous
energy transport in the RFP. A lower hybrid antenna that
operates at 800 MHz is being used in MST to assess the
feasibility of this approach. Antenna performance is
affected by plasma sawteeth indicating that the antenna and
the plasma are well coupled. The antenna has been
instrumented with pickup loops in the backplane to measure
power flow. The measured power damping length of
approximately 1-2 wavelengths is consistent with the amount
of launched power that travels completely through the
antenna structure. The damping length increases with
decreasing plasma density and is dependent on wave launch
direction. Probes capable of measuring RF fields will be
used to locate the lower hybrid wave in the plasma. In
addition, soft and hard x-ray diagnostics will be used to
look for evidence of RF-plasma interactions. Modelling with
GENRAY and CQL3D of plasma-lower hybrid wave interactions is
ongoing.
[FP1.039] Plasma Response to Oscillating Poloidal and Toroidal Current Drive in the Madison Symmetric Torus
A.P. Blair, J.K. Anderson, D. Craig, F. Ebrahimi, G. Fiksel, T.W. Lovell, K.J. McCollam, P.D. Nonn, S.C. Prager, J.C. Reardon, J.S. Sarff (University of Wisconsin Madison)
Two 1 MVA 500 Hz oscillators have been installed in the toroidal and
poloidal
magnetic field circuits of the Madison Symmetric Torus (MST) Reversed Field
Pinch.
These devices drive alternating poloidal and toroidal currents in the edge
of
the plasma affecting the current profile and thus both the spectrum of the
tearing mode fluctuations and energy confinement. We find the amplitude of
the dominant
(m=1) modes rises and falls with the oscillating edge poloidal current
while the m=0
mode amplitude appears to do just the opposite. The ion temperature also
oscillates with the edge poloidal current. The ion temperature excursion
\tildeT_i /
AC magnetic fields are applied at the shell of the Madison
Symmetric Torus (MST), and these penetrate into the plasma.
The applied poloidal and toroidal fields are used in
oscillating field current drive (OFCD).
The initial OFCD system should be capable of driving
a portion of the total plasma toroidal current.
In order to study the effects of AC field propagation within MST,
experiments are planned with several diagnostics, including
motional Stark effect spectroscopy,
far-infrared interferometry/polarimetry,
Rutherford scattering,
ion Doppler spectroscopy,
charge exchange recombination spectroscopy,
and Thomson scattering.
In previous such experiments, the normally quasi-periodic sawtooth
cycle was entrained to the OFCD cycle, and AC magnetic field
penetration toward the core was detected during sawteeth.
New experimental results are used in MSTFit equilibrium
reconstruction and compared with MHD theory.
A four-barrel cryogenic pellet injector, designed and built
by Oak Ridge National Laboratory, has been installed on MST.
The injector is a pipe gun utilizing high-pressure hydrogen
gas for acceleration of pellets. Presently, the two barrels
in use accommodate deuterium pellets with diameters of 1.0
mm and 1.8 mm and lengths ranging from 1.5 mm to 2.7 mm
which are injected radially into MST. Pellet speeds of 1300
m/s have been achieved in initial experiments, and many
pellets cross the plasma diameter without completely
ablating. The pellets rapidly increase the central density
and peak the density profile, something not possible with
gas puffing alone. Pellet injection into
improved-confinement plasmas has allowed the achievement of
line-averaged densities 10-20% larger than the usual limit,
above which edge-resonant MHD instability is triggered, and
confinement is degraded. Mechanical punches will soon be
installed to allow slower pellet speeds.
Work supported by U.S.D.O.E.
Using the full measured spectrum of the Stark-split hydrogen
emission from a diagnostic neutral beam we are able to
measure magnetic fields as low as 0.2 T in MST. A fast
liquid crystal shutter and CCD spectrometer are used to take
0.1 ms exposures of emission from a 30 keV hydrogen
diagnostic neutral beam. Recent improvements will allow 7
independent measurements of the central toroidal magnetic
field during a single shot, giving a strong constraint for
equilibrium reconstructions. Key observations to date
include a reduction of the toroidal field on axis during a
sawtooth crash of about 10profile control, the central magnetic field is measured to
increase slowly and during oscillating poloidal current
drive, very little penetration of the oscillating edge
magnetic field to the core is observed. Accuracy is
determined in part by the validity of the assumption that
the underlying components of the Stark manifold are
statistically populated and emit with fixed relative
intensities. These assumptions are being examined by
detailed atomic modeling. Work supported by U.S.D.O.E.
Measurements of the radial equilibrium potential profiles
have been successfully obtained with a Heavy Ion Beam Probe
(HIBP) in the core (0.25 < r/a < 0.75) of the Madison
Symmetric Torus (MST) Reversed Field Pinch. Typically, \phi
(r) has a magnitude of 1.0-2.0 kV in standard 380 kA
discharges. The core profile of the electrostatic potential
fluctuations \~\phi and electron density fluctuations
\~n_e(r) have also been measured in MST. The measured
\~\phi(r) ranges from 30-50 V_rms and \~n_e(r)
ranges from 10-20% for this same standard 380 kA
discharge. While most of the data obtained thus far have
been for standard discharges at a variety of plasma
currents, preliminary measurements have also been obtained
for other discharge conditions, including biased discharges
and pulsed poloidal current drive (PPCD) discharges.
Confinement is significantly improved in PPCD discharges and
HIBP measurements obtained thus far show changes in \phi
(r), \~\phi(r) and \~n_e(r). The general status of
HIBP measurements on MST will be presented including
representative data from all types of discharges and
measurement development issues.
Localized measurements of density fluctuations in the hot
core of the Madison Symmetric Torus (MST) reversed field
pinch have been made with a Heavy Ion Beam Probe (HIBP). The
density fluctuations are 10 - 20% in the region
0.25<r/a<0.75. Results are presented for both standard
and improved confinement discharges. To have confidence in
the results it is necessary to account for possible signal
corruption, such as ion path effects and electronic noise.
The HIBP on MST has 2 additional factors that are not common
to most HIBPs. The small machine ports (2" injection port
and 4.5" detection port) can result in vignetting of the
beam and the constantly changing magnetic fields causes the
beam's sample location to move. It is shown that such
instrument effects can be accounted for and are small in
selected data sets.
First measurement of the current density profile and
magnetic field fluctuations in the core of a
high-temperature reversed-field pinch are presented. We
report three new results: (1) The current density profile is
observed to peak during the slow ramp phase of the sawtooth
cycle and flatten promptly at the crash. Measured core
magnetic fluctuations are observed to increases four fold at
the crash. The fluctuating current which generates the
dominant large-scale magnetic fluctuations is measured and
found to have a spatial extent ¡Ü8 cm about the rational
surface. (2) The core magnetic fluctuations are observed to
decrease four-fold in plasmas in which the energy
confinement time improves ten-fold. (3) The parallel current
density increases in the outer region of the plasma during
PPCD. However, the current density also increases in the
core, relative to standard plasmas. Current density peaking
on axis may be explained by a reduction of the dynamo (anti)
current drive in the core. Work is supported by U.S.DOE
In the MST reversed-field pinch (RFP), experiments with
current profile control (pulse parallel current drive, or
PPCD) are routinely performed, allowing record values of
temperature and confinement time for the RFP. Recently, a
system of miniature soft-x-ray (SXR) cameras has been
installed and operated, and an overview of the resultant
tomographic data will be shown. Profiles of SXR emission
during PPCD show clear oscillations at the poloidal rotation
frequency of the innermost resonating tearing modes. An
helical coherent structure is observed with QSH spectra.
Moreover, we have observed the beating of two nearby
frequencies in the x-ray data when all MHD modes have small
amplitudes. This is consistent with the presence of two
small islands in the plasma core. It is also evidence,
reinforced by the results of the guiding center Monte Carlo
code ORBIT, that the PPCD technique is capable of reducing
magnetic chaos to the point that regions of closed magnetic
flux surfaces are produced.
Fast ion population in tokamaks is found to have a
significant influence on the dynamics of global plasma
modes. High energy particles appear to play an essential
role in the suppression of sawtooth relaxation oscillations
in tokamaks. These particles can also lead to the occurrence
of fishbone-like instabilities. In a normal mode analysis of
plasma oscillations the fast particles are described by
drift kinetic equation in which the perturbed electric and
magnetic fields are evaluated at the position of the
particle's guiding center. In this treatment the effects due
to spatial variation of perturbed fields within the
gyroradius are not considered. In reversed field pinches
(RFP) the magnetic field is an order of magnitude smaller
than in tokamaks. The Larmor radius of neutral beam injected
particles in the 10 KeV energy range in RFPs is a
substantial portion of the minor radius. The perpendicular
wave length of global plasma modes is comparable to the
Larmor radius of fast particles; thus the finite Larmor
radius effects mentioned above can be important. In this
study we concentrate on these effects only. We apply a
simple constitutive relation without drift contributions for
the fast particle dielectric response obtained from the
linearized Vlasov equation. We consider cylindrical RFP
equilibrium and use the resistive MHD model for the
description of the plasma bulk. The changes to the growth
rates of the internal modes due to the fast particles with
large gyroradius are calculated.
Measurement of impurity ion dynamics is essential for
understanding anomalous ion heating, momentum relaxation,
fluctuation induced particle transport and the MHD dynamo.
Charge exchange recombination spectroscopy (CHERS) provides
a localized measurement of the density, flow and temperature
of fully-stripped impurity ions. Standard CHERS operation in
MST uses C VI emission at 343.4 nm and is localized to +/- 1
cm. CHERS measurements with an existing Ion Doppler
Spectrometer (IDS) yield ion temperatures close to electron
temperatures, with a time resolution limited to about 1 ms.
Impurity density profiles have also been measured with this
diagnostic and are shown to have an unexpected hollow
profile. A new Ion Doppler Spectrometer (IDS II) is
currently being constructed and should increase time
resolution to at least 100 ms, to better observe
fluctuations. A Ross filtered spectrometer is also used to
view transitions to the ground state and allows for more
precise time resolved density measurements. Data of
localized time resolved density measurements using the CHERS
beam and the Ross filtered spectrometer will be presented.
Atomic modeling to consider fine structure corrections to
the CHERS line shape is being carried out and will also be
presented.
Work supported by U.S.D.O.E.
The generation of m=0 magnetic fluctuations in the reversed
field pinch (RFP) is not fully understood. Large-scale
magnetic fluctuations have been measured in the MST(Madison
Symmetric Torus) using edge magnetic coils in a toroidal
array. The ExB velocity is measured through a sawtooth cycle
using Langmuir probes and decomposed using a pseudo-spectrum
method. The measured quantities are combined to derive the
terms in the MHD equations responsible for linear excitation
of the m = 0 modes by the mean fields. Experimentally, the
magnetic fluctuation of poloidal mode number m = 0 appears
to be damped throughout the standard RFP sawtooth cycle.
This agrees with the DEBS code. Three wave nonlinear mode
coupling with m = 0 modes is measured through a sawtooth
cycle via bi-spectral analysis. The result suggests that m =
0 excitation is driven by nonlinear mode coupling, also
consistent with computation. An examination of m=0
excitation in non-standard plasma will be presented.
Work supported by U.S.D.O.E
The trajectory of an ion beam as it passes through a
magnetically confined plasma is determined by the ion mass,
energy, charge state, and the magnetic field structure. In
undergraduate physics labs, students use a measure of beam
deflection in a well defined magnetic field to determine the
charge-to-mass ratio of a particle. The complementary
analysis is equally valid: given a known charge-to-mass
ratio, the magnetic field may be determined. Additional
complexity is introduced in a spatially non-uniform, time
varying magnetic field, such as that found in a reversed
field pinch plasma. The technique of field mapping via
spectral imaging is being developed with a Heavy Ion Beam
Probe on the Madison Symmetric Torus. Spectral measurements
of emission lines of heavy beam ions, at multiple views
displaced both poloidally and toroidally from the injection
port, will be discussed. The addition of CCD cameras will
enable a three-dimensional reconstruction of the beam
trajectory through the plasma, which can be used to
determine the components of the equilibrium magnetic field.
Hyper-resistivity (a helicity-conserving current-diffusion term in Ohm's
law)(A.\ H.\ Boozer, J. Plasma Pysics, 35 (part 1), 133 (1986).), is
frequently used to model the effects of magnetic perturbations due to magnetic
islands or low-amplitude turbulent fields on current transport across mean
magnetic surfaces.
This process is important in the magnetic-field evolution of toroidal devices
such as the RFP and the edge-driven spheromak and can provide a mechanism for
sustained operation.
In previous work(H.\ L.\ Berk et al., Bull.\ Am. Phys.\ Soc.,
(Oct., 2000), paper VP1.55.), we presented a quasi-linear calculation of
the hyper-resistivity coefficient in a cylinder due to tangled magnetic
field-lines resulting from multiple tearing modes. In this paper, we present
results of simulations of the MST RFP using this hyper-resistive coefficient
in the 1 amp; 1/2 D transport code Corsica(http://wormhole.ucllnl.org/caltrans/).
Stability at the m=1 resonant surfaces is obtained from cylindrical \Delta',
and island widths are obtained from the Rutherford island equation; these are
solved self-consistently with the evolving equilibria.
We explore the resulting current profiles, in particular the steep cliff that
forms at the reversal surface, and the study the dependence on parameters.
Single helicity states in reversed field pinches are
predicted by 3D MHD simulations; similar states, called
'quasi-single helicity states', have been observed in
several experiments. Here, we explore the behavior of these
states to different dissipation rates, initital conditions,
boundary conditions, and sheared toroidal rotation. Previous
work [J. M. Finn, R. A. Nebel, C. G. Bathke, Phys. Fluids B,
(1992)] has indicated that single helicity states occur if
the dissipation is high enough. This result has been
validated by our present work which has tracked these
solutions for 10s of resistive times. Previous work has also
indicated that these states persist in less dissipative
plasmas provided that the proper initial conditions are
imposed on the plasma. Results will be presented for long
time (resistive time scale) simulations for these conditions
as well. For toroidal rotation, a narrowing of the spectrum
of m=1 modes is expected, based on the idea that nonlinear
coupling of modes drives other modes but at a phase velocity
different from the plasma velocity at the mode rational
surface of the driven mode. We will show results for these
cases also.
EXTRAP T2R is a high aspect ratio (R=1.24 m, a = 0.183 m)
reversed-field pinch device, characterised by a double, thin
shell system. The simultaneous presence of many m=1, |n|
> 11 tearing modes is responsible for a magnetic field
turbulence, which is believed to produce the rather high
energy and particle transport that is observed in this type
of magnetic configuration. In this paper first results from
current profile control experiments (PPCD) in a thin shell
device are shown. When an edge poloidal electric field is
transiently applied, an increase of the electron temperature
and of the electron density is seen, which is consistent
with an increase of the thermal content of the plasma. At
the same time, the soft x-ray emission, measured with a
newly installed miniaturised camera, shows a peaking of the
profile in the core. Furthermore, the amplitudes of the m=1
tearing modes are reduced and and the rotation velocities
increase during PPCD, which is also consistent with a
reduction of magnetic turbulence and a heating of the plasma
We discuss results concerning the application of ORBIT, a
hamiltonian guiding centre Monte Carlo code with numerical
or analytic magnetic equilibria, to Reversed Field Pinch
configurations. In particular we have analyzed the structure
of magnetic field during reduced magnetic chaos regimes
obtained with Pulsed Poloidal Current Drive experiments and
in Quasi Single Helicity conditions. The code has been used
simulating operational conditions of the RFX and MST
devices. Codes output are compared with experimental
results, in particular with tomographic imaging of the
plasma.
Three critical MHD issues are to be addressed in the course
of development of a reversed field pinch (RFP) fusion
reactor : internal tearing modes, internal and external
ideal kink modes. In STE-2 RFP [R/a=0.4m/0.1m], efforts
have been made to actively control the resistive wall
tearing modes with external rotating helical field (RHF).
Without RHF, core resonant mode (m=1/n=8) grows with time
scale of \tau_w, and identified as the resistive wall
tearing modes. The resonant mode, which otherwise is locked
to the wall, rotate with the applied RHF with perturbation
level of \sim0.4 %, and that the applied RHF has an
influence on the rotation of the neighboring modes as well.
When we increase the perturbation amplitude up to 0.6 %,
the pinch parameter \Theta sometimes increases to higher
than 2.5. The high-\Theta operation is the result of
plasma current increase more than toroidal flux. In this
high-\Theta regime, the resonant mode sometimes rotates in
the direction of plasma current at the same velocity as the
applied RHF, while the neighboring modes rotate at lower
velocity. The time averaged fluctuation level of the
dominant modes remains lower than in the case without RHF.
One of the interesting features in high-\Theta regime RFP
is that m=1/|n|=3,4 modes grow with the time scale of
\tau_w. The behavior will be discussed in comparison with
linear stability of external kink modes.
The effects of multiple resistive shells and transient
electromagnetic torque on the dynamics of mode locking in
the RFP plasmas are studied. We study the EM torque acting
on the tearing modes produced by a system of resistive
shells. These shells may consist of several nested thin
shells or several thin shells enclosed within a thick shell.
Both the steady state theory and the time dependent theory
are developed. The steady state theory is shown to provide
accurate account of the resultant EM torque if
(dømega/dt)ømega^-2 <<1 and if the time scale of
interest is much longer than the response (L/R) time of the
shell. Otherwise, the transient theory should be adopted. We
begin with the study of a single representative dynamo mode,
in which the steady state theory is used to evaluate the
changes of the EM torque induced by the resistive shells in
two variants of two RFP machines: 1) RFX and the modified
RFX; 2) T2 and T2R. The transient theory has been applied to
study the time evolution of the EM torque during the
unlocking of a locked tearing mode in the modified RFX. In
addition, the effects of non-linear mode coupling is added
to the study of the interaction between the resistive walls
and the multiple modes. The formation of the slinky mode and
its dynamics in the presence of resistive walls are
discussed.
A study of plasma dynamics during Pulsed Poloidal Current
Drive (PPCD) in the reversed field pinch is conducted with
non-ideal magnetohydrodynamic simulations in cylindrical and
toroidal geometry using the NIMROD code
[http://nimrodteam.org]. Finite pressure simulations at a
Lundquist number of S\sim2000 show a marked reduction in
core-resonant dynamo activity and increases in instantaneous
energy confinement time commensurate with applied poloidal
electric field strength (up to 66% increase in the
strongest electric field case). A mode-decomposition study
with varied numbers of toroidal Fourier components and an
analysis of the contributions to Ohm’s law uncovers the
dominant mechanisms governing the parallel current profile
evolution. Computational studies at S-values greater than
2000, including a scaling study of the effects of Lundquist
number on magnetic fluctuation reduction, is underway. We
are also investigating how shaping the poloidal cross
section affects nonlinear fluctuation amplitudes and
coupling in the absence of PPCD.
We are developing a statistical treatment of an RFP MHD
turbulent dynamo. This requires a closure to end the
nonlinear chain of equations for the multipoint
correlations. In the simplest case of homogeneous,
isotropic, mirror-symmetric fluid turbulence, one focuses
only on the elements of the energy spectrum because
translational invariance guarantees the vanishing of
A so-called "dynamo" mechanism, due to co-operation of
fluctuating velocity and magnetic fields, is usually seen as
essential to describe the sustainment and transport of the
Reversed Field Pinch (RFP) confinement configuration. 3D MHD
nonlinear numerical simulations (SpeCyl code) are discussed
in this work where an external drive is applied, similarly
to the action of an experimental Pulsed Poloidal Current
Drive (PPCD)[1,2]. The PPCD technique has been
experimentally proven to provide substantial reduction of
heat transport. In this work we show that, during the
external action, the MHD (dynamo) perturbations decrease in
amplitude and that the current density profiles become
steeper and in particular increase in the central region, as
observed in experiments [1,2]. Moreover we stress the
importance of the pinch velocity term which yields the most
important contribution in balancing the resistive diffusion
when the turbulent dynamo becomes negligible in Ohm’s law.
[1] Puiatti et al. , to be submitted to 19th IAEA 2002
conference [2] D.L.Brower et al. , Phys.Rev. Lett., 88,
185005 (2002)
What is the minimal information that must be supplied on a
constant pressure surface of a toroidal plasma to completely
specify a local magnetohydrodyamic equilibrium? Clearly the
shape of the surface must be specified, but other
information such as the separation between neighboring
surfaces must also be given. We explore the conditions
required for three dimensional equilibria and how local
equilibrium constraints are related to global constraints.
The resulting conditions provide useful checks on the
accuracy of equilibrium solvers, particularly for solvers
for three-dimensional equilibria, and allow local
refinements in the accuracy of equilibria. Work supported by
the U.S. Department of Energy under Grant No.
DE-FG02-95ER54333.
In tokamaks some major disruptions can be ascribed to
nonlinear coupling of m/n=2/1 tearing mode with another
tearing mode. Especially for ohmically heated high current
tokamak plasmas, coupling of m/n=1/1 and 2/1 tearing modes
can ergodize magnetic fields in large regions of plasmas,
which would lead to significant damage to the confinement.
In this work we have examined the conditions for strong
coupling of m/n=1/1 and 2/1 tearing modes due to finite beta
and aspect ratios, using the three-dimensional simulation
code based on reduced MHD equations in toroidal and
cylindrical geometries. The code uses the finite-element
method(FEM) in the poloidal plane and Fourier decomposition
in the toroidal direction with unstructured triangular
elements and piecewise linear basis functions. The advantage
of this code is that it allows us to examine nonlinear
evolution of plasmas with arbitrary cross-section shapes. We
shall also present results of linear stability analyses of
those tearing modes using the FEM code as well as a
circular-cross section cylindrical spectral code.
Analysis of the ideal MHD n=1,m=1, instability where n and m
refer to the toroidal and poloidal mode number, is usually
based on fixed boundary conditions. This effectively
suppresses a source of free energy, the finite boundary
perturbations. Inclusion of this effect reduces the
threshold for instability. We report on details of this
effect. Another aspect of the internal kink which requires
detailed numerical studies is the details of the plasma
profiles in the core region. Commonly accepted criteria are
based only on the pressure gradients inside the q=1 surface.
Here we report on the importance of the shear, q', as well
as p'. An empirical criterion for stability is shown. This
work was supported by DoE Contract No. DE-AC02-76-CHO-3073
The macroscopic internal mode with poloidal and toroidal
numbers m=n=1 plays an important role in the confinement
properties of tokamak plasmas. It is the driver of the
sawtooth oscillation as well as a laboratory example of fast
reconnection. Meaningful fusion burn experiments are
designed to operate with large plasma currents that
correspond to relatively low values of the magnetic safety
factor q and to a significant volume of plasma enclosed in
the q=1 surface. This has a destabilizing influence on the
m=n=1 mode and increases the deleterious effects of
sawtooth crashes. In fusion ignition experiments, the ideal
m=n=1 mode will typically be at best weakly unstable or
close to ideal marginal stability due to the high values of
the plasma pressure needed for fusion burning. For plasma
regimes relevant to the Ignitor experiment [1], the marginal
stability threshold for ideal MHD has been computed using
the PEST code [1] (courtesy of J. Manickam). We focus then
on those cases where resistivity controls the linear
instability. We summarize the analytical results obtained in
the low-\beta reduced MHD framework and present a
numerical study of the onset of nonlinear effects using the
3D MHD initial value code M3D [3]. [1] B. Coppi and A.C.
Coppi, Nucl. Fusion 32, 2 (1992). [2] R.C. Grimm, R.L. Dewar
and J. Manickam, J. Comput. Phys. 49, 94 (1983). [3] W. Park
et al., Phys. Plasmas 6, 1796 (1999).
The two-fluid effect on a m/n=1/0 kink instability in a
cylindrical tokamak with negative central current density is
examined numerically. It is known that a m/n=1/0
resistive-kink instability removes a negative central
current density, and then it flatten the current density.
This flattening can explain the formation of current hole,
which is a region with a very small toroidal current around
a magnetic axis in strongly reversed shear tokamaks. The
two-fluid effect such as electron inertia dominates this
magnetohydrodynamics in high temperature tokamak plasmas.
This effect induces a non-linear secondary magnetic
reconnection, thereby recovering a negative central current.
The Porcelli model for sawtooth oscillations(F. Porcelli,
et al.,) Plasma Phys. Control. Fusion 38, 2163 (1996),
which provides a set of criteria for the triggering of sawtooth
oscillations, has been implemented in the 1\frac12D BALDUR
integrated predictive modeling code. In this code, sources, sinks
and transport are computed self-consistently. In the Porcelli
sawtooth model, sawteeth are triggered by any of three criteria
for the m=1 mode: 1) kink modes when stabilization by fast ion
precession fails, 2) kink modes when diamagnetic rotation
stailization fails, and 3) drift tearing modes localized near the
q=1 magnetic surface, when stabilization by kinetic layer and
rotational effects fails. BALDUR simulations of JET and DIII-D
discharges using the theory-based Multi-Mode transport model
(MMM95) indicate that most of the sawteeth are triggered by the
third criterion, and this criterion is found to be sensitive to
the relative amount of magnetic reconnection during each sawtooth
crash. The trigger is less frequent when there is more magnetic
reconnection. The sawtooth period predicted by the Porcelli model
in BALDUR simulations fluctuates in time, which is also observed
in experiments.
\vskip4pt ^Supported by DoE contract
DE-FG02-92-ER-54141
equilibrium, energy and particle transport fluxes, sources such as
neutral beam heating, sinks such as impurity radiation, and the results
of large scale instabilities such as sawtooth oscillations in tokamak
plasmas.
The M3D code has been applied to
ideal, resistive, two fluid, and hybrid
simulations of
quasi axisymmetric stellarators and tokamaks.
Ideal and resistive ballooning modes with moderate
toroidal mode number
(n \sim 10 ) have been studied in an NCSX design.
The resistive modes occur well below the ideal \beta
limit, and have growth rate scaling with resistivity \eta
similar to tearing modes. When two fluid gyroviscous
effects are included nonlinearly in the simulations,
the resistive modes are stabilized. The two fluid
simulations were done with a realistic value of
the ratio of ion skin depth to major radius,
c / (ømega_pi R) = 0.01.
At this value
high mode number ideal modes should also be stabilized,
which can have a significant
effect on the \beta limit.
Hybrid gyrokinetic simulations
with energetic particles have been done
in a two - period compact stellarator geometry.
A predominantly n = 1 toroidal mode was found with
the frequency
of a TAE mode, with growth rate linear in the energetic particle
\beta.
Increasing the deviation from axisymmetry
(deforming a tokamak into a stellarator) has a stabilizing
effect.
Simulations are in progress incorporating an external
vacuum magnetic field with an axisymmetric resistive wall,
in order to study halo currents in
ITER. The simulations include self consistent resistivity and
density evolution, in which the vacuum region between the plasma
and resistive wall is modeled by high resistivity and low density.
The energetic particle-driven MHD modes are studied using hybrid model
of the M3D code.
The previous version of the M3D code was mainly
applied to axisymmetric circular tokamak geometry.
Recently we have extended the M3D code to full 3D geometry using
unstructured mesh in poloidal planes and finite difference in
toroidal direction. The code has also been parallelized so it can run in parallel
using OpenMP or MPI. These new capabilities enable us to simulate
fast ion-driven Alfven modes in advanced tokamaks, spherical tokamaks and
stellarators for realistic parameters.
First, fast ion-driven Alfven modes in spherical tokamaks are studied.
Simulation results show an n=1 TAE mode destabilized by fast ions at low
plasma beta. However, as plasma beta increases, the mode frequency reduces
to a low value at about 25% of the TAE frequency.
Second, fast ion-driven Alfven modes in quasi-axisymmetric stellarators are
studied. For a two period stellarator, results show an unstable global TAE
mode with n=1 as the dominant toroidal mode number. The effects of 3D shape
is found to be stabilizing. Third, alpha-driven TAE/EPM and alpha particle effects on internal kink mode in burning plasmas are
studied. Initial results indicate high-n TAE/EPM are stable in FIRE.
Nonlinear simulation with the M3D code
shows that two-fluid effects
are crucial to predicting steady states
in the proposed NCSX ``quasi-axisymmetric'' stellarator,
at realistic values of the two-fluid parameter H=1/(Ømega_ci\tau_A).
In MHD at H = 0, barely unstable ideal ballooning modes grow with a
resistive contribution near the low-field edge of the
plasma, with toroidal mode numbers n\sim 10.
Outer magnetic surfaces may be lost over a considerable radius.
For H\ne 0 and p_i\ne 0,
ion diamagnetic effects generate a poloidal shear flow of
the plasma mass relative to the magnetic configuration and
robustly suppress the modes, even at very large resistivities.
If p_e\ne 0, enhanced reconnection due to electron two-fluid
effects is observed in faster island formation at low order rational
magnetic surfaces.
At higher beta, the ion flow continues to suppress ballooning modes,
but magnetic island growth is also faster and may distort the
configuration sufficiently to lose the flow stabilization.
The achievable steady state beta and magnetic configuration
is thus limited by two-fluid effects.
Similar suppression of mode growth due to ion diamagnetic effects
and nonlinear enhancement of magnetic island growth by electron effects,
due to the parallel gradient of the electron pressure in the Ohm's law,
occurs in tokamaks.
\leftline*Sponsored by the U.S. Department of Energy.
Neoclassical tearing modes have received significant interest
in the experimental and theoretical communities because they
significantly limit the performance of long-pulse plasma discharges.
Many theoretical and experimental questions remain, one of which is the
role of the \Delta' parameter, first introduced in the study of
classical tearing modes.
To isolate the effects of this parameter experimentally, recent
experiments(M.S. Chu and R.J. LaHaye - private communication)
that produce tearing modes have been performed in low pressure, Ohmic
discharge
on the DIII-D tokamak. Using a recent experiment with modern
diagnostics and accurate equilibrium reconstruction provides
an excellent opportunity for accurate comparison of theory with
experiment. Preliminary NIMROD
modeling of this experiment based on EFIT equilibrium show that
a vacuum region is needed to model this experiment. Because
NIMROD is a nonlinear, initial-value code which must allow for
a moving separatrix, NIMROD models the ``vacuum'' region as
a cold, highly-resistive plasma. Here, we present results from
NIMROD's modeling of this experimental discharge using a
three-dimensional resistivity which varies with time.
The ordering that
\rho_i \ll L_eq
enables us to use the
gyrokinetic description for a magnetically-confined plasma,^1-3
by seperating the fast gyromotion of the particle from
its slow gyrocenter motion and the associated polarization effects.
In this paper, we present a brief comparison of the properties of the
Alfvén waves based on the conventional MHD
descriptions with those under the gyrokinetic
approximation, and show that the unique treatment of
the polarization effects in the gyrokinetic formalism makes it possible to
eliminate the compressional Alfvén waves without resorting to
geometric simplification for the reduced gyrokinetic-MHD equations.
Thus, one may use the existing gyrokinetic particle
simulation techniques^1,4-5 together with the elliptic multigrid
solver^6
on the modern day massively parallel computers to study the effects of
neoclassical and microturbulence transport on the
global (MHD) problems based on the realistic MHD equilibria.
\$This work is supported by the US DoE SciDAC project.
\$^1W. W. Lee, Phys. Fluids 26, 556 ('83);
J. Comp. Phys. 72, 243 ('87).
\$^2T. S. Hahm, W. W. Lee and A. Brizard, Phys. Fluids 31, 1940
('88).
\$^3H. Qin, W. M. Tang and W. W. Lee, Phys. Plasmas 7, 4433 ('00).
\$^4I. Manuilskiy and W. W. Lee, Phys. Plasmas 7, 1381 ('00).
\$^5W. W. Lee, J. L. V. Lewandowski, T. S. Hahm, and Z. Lin,
Phys. Plasmas 8, 4435 ('01).
\$^6J. L. V. Lewandowski, manuscript in preparation.
A study\footnotetext[1]This work is supported by US DoE contract
DE-AC02-76CH03073. is presented for the stability of \alpha
-particle driven shear Alfvén Eigenmodes (AE) for the three burning
plasma proposals, ITER, FIRE and IGNITOR. An analytic assessment of TAE
stability is first presented and stability boundaries are
determined. Then the High-n stability code HINST is used. HINST computes
the non-perturbative kinetic solutions of the Alfvén eigenmodes. The
stability calculations are repeated using the global code NOVAK. We show
that for these tokamaks the spectrum of the least stable AE modes,
TAEs, appears at medium-/high-n numbers. In HINST, TAEs are locally
unstable due to the alphas' pressure gradient in ITER and FIRE. However,
NOVAK calculations show that the global mode structure enhances the
damping mechanisms and produces stability in all configurations
considered here. A serious question remains whether the perturbation
theory used in NOVAK overestimates the stability predictions, so that it
is premature to conclude that the nominal operation of all three
proposals are stable to AEs. In addition in ITER the beam energy is
high so that the beams induce a destabilizing effect on TAEs.
Interaction between Alfvén waves and energetic ions is a
very important issue in a fusion research. One of important
issues in Alfvén eigenmodes(AE) studies is to directly
measure the damping rate of AEs. For this purpose, the
excitation of toroidicity-induced Alfvén eigenmodes(TAE)
was attempted by externally applied magnetic perturbations
in the range of 100\,\mathrmkHz in a low temperature and
low density plasma of the Compact Helical System(CHS)
heliotron/torsatron. The magnetic perturbations are
generated by oscillatory currents that are induced along the
magnetic field line by two electrodes arranged in the
toroidal direction. When the frequency of the oscillatory
current is swept in time, the ratio of induced magnetic
fluctuations to the induced currents clearly exhibits a
character of the resonance at the frequency ømega_0. The
frequency ømega_0 agrees well with the TAE gap frequency.
The measured damping rate \gamma_\mathrmd/ømega_0 is
about 10%. This large damping rate is thought that the
eigenfunction of the excited TAE extends toward the plasma
edge and would interact strongly with shear Alfvén
continuum there.
It is shown that low-m magnetic islands have significant
effects on the formation of the transport barriers in recent
LHD experiments. A numerical simulation code has been
developed for studying nonlinear evolution of interchange
mode in the presence of a vacuum magnetic island. Three
field RMHD equations for stellarators are solved here. As a
numerical method, two dimensional finite element method is
used in the poloidal cross-section. Nonlinear pressure
driven modes in a heliotron configuration have been solved
in a cylindrical geometry. In this work, the (m,n)=(1,1)
vacuum island is introduced with an assumed non-zero value
for the boundary condition of magnetic flux, \Psi_B. The
width of vacuum island may be controlled with changing the
magnitude of \Psi_B. The effect of vacuum island for the
growth rate of n/m=1/1 mode is destabilizing. The
mechanism to change the growth rate as well as the change of
eigenfunction is discussed. Also nonlinear behavior will be
shown in the poster.
The DCON code is in wide use for computing the ideal MHD stability of
axisymmetric toroidal plasmas. It uses an adaptive numerical integrator
to solve a system of ordinary differential equations for the radial
dependence of complex Fourier coefficients of the normal displacement, a
generalization of Newcomb's equation, from the magnetic axis to the
plasma-vacuum interface. Fixed-boundary stability is determined by a
toroidal generalization of Newcomb's criterion. Free-boundary stability
is determined by the sign of the lowest eigenvalue of the sum of plasma
and vacuum response matrices. DCON has been extended to compute the
outer ideal region matching conditions for singular modes such as
resistive and neoclassical tearing modes. A matching matrix is
constructed from asymptotic coefficients of resonant and nonresonant
solutions on either side of each singular surface and corresponding
terms from any singular surface model. A dispersion relation for growth
rates and eigenfunctions is obtained from the roots of the determinant
of this matrix. A new, more accurate method for crossing the singular
surface has avoided numerical errors affecting previous efforts to
accomplish this. Benchmarks with the PEST 3 resistive stability code
will be presented.
An adaptive eigenvalue linear stability code is developed.
The aim is on one hand to include the non-ideal MHD effects
into the global MHD stability calculation for both low and high n
modes and on the other
hand to resolve the numerical difficulty involving MHD singularity
on the rational surfaces at the marginal stability.
Our code follows some parts of philosophy of DCON
by abandoning relaxation methods based
on radial finite element expansion in favor of an efficient shooting
procedure with adaptive gridding. The \delta W criterion is
replaced by the shooting procedure and subsequent matrix eigenvalue
problem. Since the technique of expanding a general solution
into a summation of the independent solutions employed, the rank
of the matrices involved is just a few hundreds. This makes easier to
solve the eigenvalue problem with non-ideal MHD effects,
such as FLR or even full kinetic effects, as well as plasma rotation
effect, taken into account. To include kinetic effects,
the approach of solving
for the distribution function as a local eigenvalue ømega problem
as in the GS2 code will be employed in the future.
Comparison of the ideal MHD version of the
code with DCON, PEST, and GATO will be discussed. The non-ideal MHD
version of the code will be employed to study as an application
the transport barrier physics in tokamak discharges.
Relativistic two-fluid equations have been recently
developed by Hazeltine and Mahajan(Hazeltine, R.
D., and S. M. Mahajan, Ap. J. 567) (2), 1 (2002),
which extend the models of MHD and of Chew, Goldberger, and
Low with a new closure procedure that is valid in regions of
low collisionality and high (relativistic) velocities and
temperatures and that includes parallel heat flow and
pressure anisotropy as essential components. Since these
equations include a richer class of phenomena than the usual
MHD equations, and since both anisotropic pressure and
parallel heat flow are essential components of the theory,
these equations present unique numerical challenges. We
present a computational plan to begin initial numerical
exploration of this interesting system.
In particle simulations of electromagnetic plasma
perturbations, the perturbed fields are frequently expressed
in terms of the potentials \phi and
\mathbfA_\parallel. An alternative choice is \phi
and \mathbfA_\perp or equivalently \mathbf\xi =
( \mathbfb \times \mathbfA )/B, with
\mathbfA_\parallel = 0. The vector \mathbf\xi
is related to the magnetic field line displacement and
\nabla_\perp \cdot \mathbf\xi to field line
compression. Plasma kinetic equations are derived in terms
of these variables and Maxwell's equations are formulated so
as to require the evaluation of the plasma pressure rather
than the plasma current. The linearised eigenmode equations
are essentially quasi-neutrality for \phi and the
conventional linearised MHD fluid equations for
\mathbf\xi. Kinetic and nonlinear effects are included
by integrating the drift-kinetic (or gyrokinetic) equation
to calculate the charge density and that part of the
perturbed plasma pressure which depends on the details of
the particle guiding center motion. The suitability of these
equations as the basis of a particle simulation code is
explored.
In recent years, increasing interest has been devoted to the properties of
flowing plasmas. It is well known that bulk plasma rotation and sheared
flow improve MHD stability (m = 1, wall mode and ballooning) and
reduce turbulent energy transport. Plasma rotation can be self-generated or
driven by parallel injection of neutral beams. The combination of a tight
aspect ratio and fast toroidal rotation in NSTX leads to MHD equilibria
that are considerably different from static ones. If the toroidal flow is
of the order of the sound speed, the density and pressure are squeezed
outward by the centrifugal force. Additional complications arise when
pressure anisotropy and finite poloidal flows are included in the
computation. For instance, when the poloidal flow is of the order of the
poloidal sound speed [C_s\theta = C_sB_\theta/B], the pressure,
density, and velocity profiles develop radial discontinuities at the
transonic surface. Here, we present a new equilibrium code (FLOW) for the
solution of MHD anisotropic equilibria with arbitrary poloidal and/or
toroidal flows. When pressure anisotropy is included, the equilibrium
depends on six free functions that need to be assigned as input. The code
is used to determine NSTX equilibria with fast (sonic and supersonic)
toroidal flow and pressure anisotropy. This work was supported by the U.S.
DOE Office of Inertial Confinement Fusion under contract DE-FG02-93ER54215.
Improved formalisms of equilibrium and stability analyses of flowing
two-fluid MHD have been developed in which the generalized vorticity of each
species is introduced as a characteristic quantity. These extend the
conventional single-fluid MHD. Equilibria with purely azimuthal ion flow are
studied analytically and numerically. ST and CT equilibria which are
relevant to the current experiments are found. These equilibria have many
characteristics which can be described by the single-fluid. Criteria are
found for when the single-fluid is adequate and when the two-fluid is
necessary. The two-fluid is needed for equilibria with a) smaller
characteristic length, b) higher beta value, and c) ion flow closer to the
ion diamagnetic drift. A new relation between the perturbation of the
generalized vorticity and the displacement vector for each species is found.
The eigenvalue equation for two-fluid stability implies that 1) not only the
magnetic field but also the generalized vorticity and 2) the electron flow
as well as the ion flow may affect the stability for system with moderate
size.
Disruptive high \beta tokamak plasmas can be stabilized
by the addition of a sheared toroidal flow. Nonlinear
simulations demonstrate that confinement in flow-free high
\beta tokamaks is rapidly destroyed by growing fingers
of hot plasma that jet out from the the center of the
discharge to the wall. The added toroidal flow can eliminate
the fingers and restore confinement. As \beta is
increased further, the toroidal flow becomes less effective
at maintaining a stable plasma. But a sound speed toroidal
flow can increase the critical value of \beta below
confinement is maintained without disruption.
A theoretical study for the feedback stabilization of
resistive wall modes (RWM) is presented in a toroidal
geometry. A general eigenvalue formulation describing the
dispersion relation of resistive wall modes in a toroidal
geometry in the presence of a set of stabilizing discrete
feedback coil currents is developed. The coupling effects
between the toroidal eigenmodes and a set of discrete
stabilizing coil currents are included. The formalism is
then applied to the proposed KSTAR plasmas and segmented
FEC/RWM coil system to evaluate the maximum achievable
plasma beta and power supply requirements for the feedback
coil system.
The Floquet stability of systems of differential equations
with piecewise constant periodic coefficients is considered.
In the "two-step" case the monodromy matrix is the product
of two matrix exponentials. It can be evaluated either by
reducing the matrix exponentials to polynomials on the
eigenvalues of the corresponding matrices or, without
knowledge of the eigenvalues, by using the
Baker-Campbell-Hausdorff formula. The two methods are
discussed and applied to several examples including the
"two-step" dissipative Hill's equation introduced recently
(see [1]) to stabilize the "resistive wall mode" in
magnetically confined plasmas. [1] H. Tasso and G.N.
Throumoulopoulos, Physics of Plasmas 9, 2662 (2002).
We present studies of feedback applied to resistive wall
modes in the presence of plasma rotation. The main tool used
is a Newton-Krylov nonlinear reduced resistive MHD code with
completely implicit time stepping[1]. The effects of
proportional and derivative gain and toroidal phase shift
are investigated. In addition to studying the complete
stabilization of the resistive wall mode, we present results
on controlling the amplitude of nonlinear modes locked to
the wall but propagating slowly; we also show results on
reducing the hysteresis in the locking-unlocking bifurcation
diagram.
[1] L. Chacon, D. A. Knoll and J. M. Finn, "An implicit,
nonlinear reduced resistive MHD solver", J. Comp. Phys. v.
178, pp 15-36 (2002).
We present further results of our modeling of the feedback
stabilization(M.S. Chance, et. al.,
\textitTheoretical modelling of the feedback stabilization
of external MHD modes in toroidal geometry), Nucl. Fusion
\textbf42 (2002) 295-300; M. S. Chu, et. al,
\textitNormal mode approach to the modelling of the
feedback stabilization of the resistive wall mode,
submitted to Nucl. Fusion of the resistive wall mode in
tokamaks. We have studied the effects of different sensor
coil orientations, and have also made progress in exploring
the advantages of placing the the feedback coils inside the
resistive vacuum vessel. The formulations and results will
be presented.
Dynamic Ergodic Divertor (DED) is an advanced concept for
the control of the tokamak edge plasmas. In contrast to
conventional Ergodic Divertor, an externally applied helical
magnetic field rotates in the helical direction. This
rotating helical field (RHF) may decrease the heat and
particle flux onto the local target in the conventional
divertor. In the DED experiment, it is also expected that
RHF induces the edge plasma rotation due to the shielding
current around the resonance surface. Penetration processes
into tokamak plasmas and dynamic behavior of RHF have been
investigated on HYBTOK-II tokamak. We have confirmed the
attenuation of the radial component of RHF from the magnetic
probe measurement. When the relative rotation velocity
between the plasma and RHF is small around resonance
surface, however, the radial component of RHF is amplified
by the effect of re-distribution of the plasma current by
island formation. We will analyze the penetration process of
RHF by linear MHD theory.
A two- dimensional MHD code has been developed to simulate the temporal
evolution of Tokamak plasmas with an imposed poloidal flow. The code is
fully compressible and can resolve the shock structures arising when the
poloidal velocity is of the order of the poloidal sound speed
(V_\theta\sim C_s B_\theta/B) near the plasma edge, where the plasma is
cold and the sound speed is low. The poloidal flow is assigned as an
initial condition with a velocity profile ranging from subsonic to
supersonic near the edge. It is found that a continuous band of shocks is
formed near the edge. Such shocks travel poloidally, leaving behind a
pedestal structure similar to the one predicted in Ref. 1 [R. Betti and J.
P. Freidberg, Phys. Plasmas 7, 2439 (2000)]. Here, the pedestal is
defined as a sharp discontinuity in the pressure, temperature, and density
profiles. The pedestal height is modulated in the poloidal angle; it is
maximum on the outboard side (\theta = 0) and minimum on the inboard
(\theta = \pm\pi). Furthermore, both poloidal and toroidal flows develop
a shear layer at the location of the pedestal. The large velocity shear
(both poloidal and toroidal) occurring in the pedestal region is likely to
suppress turbulent eddies and reduce anomalous transport. This work was
supported by the U.S. Department of Energy Office of Inertial Confinement
Fusion under Cooperative Agreement No. DE-FC03-92SF19460.
It is shown that a magnetic island in a one-dimensional
equilibrium plasma, such as a cylindrical plasma or a slab
plasma can induce a pressure-gradient-driven current
parallel to the magnetic field similar to the bootstrap
current in toroidal plasmas. This current flows on both
sides of the island in opposite directions. It modifies the
current density profile that drives the island growth in the
vicinity of the island and may provide a mechanism for
island saturation in such plasmas. The magnetic island
induced plasma viscosity damps the helical component of the
plasma flow velocity. This alters the polarization drift.
The polarization drift also has opposite signs on both sides
of the island. The plasma electrical conductivity is reduced
due to the existence of trapped particles when the island
width is finite. The implications on tokamak neoclassical
island will be discussed.
Suydam/Mercier criterion demarcates the instability boundary
of a toroidally confined plasma for a radially-localized
pressure-driven ideal MHD interchange instability. Many
present day tokamaks operating in high performance regimes
(i.e., high \beta) are very close to the ideal stability
boundary. In this work, we address the nonlinear evolution
properties of Suydam modes as the stability boundary is
violated. Linear stability analysis of the pressure-driven
ideal interchange instability indicates a very weakly
growing mode since the growth rate is negligibly small well
above the marginal stability condition (i.e., Suydam
criterion)(Violating Suydam criterion produces
feeble instabilities, Sangeeta Gupta, J. D. Callen and C. C.
Hegna, report UW-CPTC 01-7 (to be published in Phys.
Plasmas.)). The nonlinear behavior of these weakly growing
modes is still an unanswered question. For studying the
nonlinear fate of these modes, the nonlinear vorticity
equation coupled with the ideal Ohm's law and pressure
evolution equation are solved numerically using a Galerkin
representation. Here, only the equilibrium, fundamental
growing mode and its second harmonics are evolved in both
space and time. Numerical results indicate that at later
times a large current density appears around the
mode-rational surface. The role of various nonlinearities,
especially the nonlinear term in the Ohm's law, in the
generation of this large current density will be discussed.
Low mode number (n < 3) instabilities in toroidal plasmas
are governed by ideal, resistive or neoclassical MHD
descriptions in which both the electrons and ions have
fluid-like responses. In contrast, very high mode number
modes (n > 30) have near-adiabatic electron responses, are
governed by kinetic descriptions, and usually are of the
drift wave type. In this work we explore a ``hybrid MHD"
description of medium mode number modes (3 < n < 30) in
which the ions are always fluid-like but the electrons are
kinetic on short parallel scale lengths (within one
connection length \sim R_0 q) but fluid-like on long scale
lengths (>> R_0 q). The key to such a hybrid description
is a Chapman-Enskog-type, ``neoclassical-like" kinetic
derivation of the collisional (ømega \leq \nu_e) electron
response for such mode numbers. The stress and heat flow
moments of this kinetic electron response yield the parallel
viscous force and heat flux moments that are needed to close
the fluid moment equations. These closure moments include
electron Landau and flow damping effects. Hybrid MHD
ballooning instabilities are then sought using a combination
of the pressure balance, parallel Ohm's law and
quasineutrality (or current-continuity, \nabla \cdot
J = 0) equations.
We investigate the dynamics of Taylor relaxation with
the aim of elucidating general/universal characteristics.
The argument of Boozer is extended to derive a
model-independent 1D nonlinear pde for the transport of
helicity density during Taylor relaxation in an
inhomogeneous system (i.e. an R.F.P.). Imposing joint
reflection symmetry further constrains the form of the
helicity flux, and yields, in the large scale limit a
simple, 1D equation for the time evolution of deviations of
the current profile from the Taylor state. This equation
extends the time-honored concept of hyper-resistive
diffusion, and is perhaps the minimal model of Taylor
relaxation dynamics. We have examined the implications of
the model, in both a `coherent' and `stochastic' framework.
In the coherent case, it is easily shown that all localized
current perturbations decay time asymptotically. However,
stationary current dipole pairs and traveling wave
solutions exist. In the stochastic context, we derive a
scaling relation between the effective magnetic Reynolds
number and the noise intensity. This scaling is being
compared with astrophysical data. The relation of traveling
wave solutions and avalanches to relaxation transients will
be discussed.
The MHD dynamics of ac magnetic helicity injection is
investigated using 3-D computation at Lundquist numbers up
to 500, 000 in the Reversed Field Pinch (RFP). To date most
of the MHD computations have been based on the dc helicity
injection. We model Oscillating Field Current Drive (OFCD,
also called F-theta pumping), a form of ac helicity
injection, in which toroidal and poloidal oscillating
voltages are applied at the plasma surface to inject
magnetic helicity and sustain steady-state plasma current. A
3-D nonlinear, resistive MHD code (the DEBS code) is used to
examine the penetration of driving oscillating fields, the
response of the both oscillating mean profiles and the
helical tearing instabilities during a cycle, and the cycle
averaged response. We study both current sustainment by
oscillating fields when mean toroidal voltage is zero
(helicity replacement) and partial current sustainment in
the presence of ohmic drive (helicity addition). In the
absence of tearing fluctuations (1-D response) a
steady-state axisymmetric edge current is driven by the
dynamo effect of the axisymmetric oscillating fields. It is
shown that in the 3-D computation, the total toroidal plasma
current can be fully sustained by OFCD helicity replacement.
With the full 3-D response, resisitive MHD fluctuations
(turbulence) relax the driven edge current toward the center
(by the tearing mode dynamo), resulting in a steady-state
current over the entire plasma cross-section. Partial
current sustainment can be obtained by OFCD helicity
addition. The dependency of the F-theta oscillations on
frequency, as well as the oscillating amplitudes dependency
on Lundquist number, S, are shown. Although the computations
show that oscillating fields can drive significant amount of
current, because of the excitation of the edge modes,
fluctuations are enhanced during part of the cycle. We show
that the resonant edge modes are excited linearly due to the
large oscillations in the mean profiles. Using the field
line trajectories, the magnetic field line stochasticity is
also investigated for the current sustainment by oscillating
fields.
Based on the symmetry between plasma flow and magnetic
field, a new physically possible assumption about internal
plasma current distribution is used to show that magnetic
structures with closed flux surfaces can exist in flowing
plasmas. The introduced assumption and the resulted new
magnetic structures give new meanings and perspective to an
ideal MHD framework initiated by Chandrasekhar in the 1950s.
It is argued that the new assumption is not a natural result
of the variational principle. The proposed magnetic
structure family includes well-known prototypes, such as
Taylor-state spheromaks, field-reversed configurations
(FRCs), and an infinite number of other new members. New
examples are discussed in detail. To obtain these magnetic
structures, the role of plasma flow is critical. Because of
the non-vanishing plasma flow, the proposed
magnetic-structure-inbedded plasma states are different from
conventional ones. For example, the new spheromak solutions
can have non-vanishing electromagnetic force, finite plasma
pressure gradient, and plasma flow, while its conventional
counterpart is a force-free state with zero pressure
gradient and no plasma flow. Based on these new structures,
new fusion schemes that rely on the plasma flow and magnetic
field self-organization might be possible. New
interpretation of fusion experimental data is also possible
using these proposed magnetic structures. In addition, the
proposed magnetic structures might find their applications
in explanation of cosmic magnetic objects.
In the tokamak startup phase, a large temporal magnetic flux
change is required for having sufficient loop voltage inside
the vacuum vessel. The large flux change causes large eddy
currents flowing in various conducting structure materials
such as vacuum vessel, passive stabilizer, toroidal
conducting loops for compensating the connection of adjacent
toroidal field coils, etc. The vacuum magnetic field
structure may be significantly influenced by the eddy
currents. For efficient inductive startup, it is important
to control the field geometry especially at the initial
startup phase in a tokamak. With an exemplary tokamak
geometry, we studied the generation of field null inside the
vacuum vessel including several driving currents and induced
eddy currents in structural materials. Under such
circumstances, the evolution of plasma parameters such as
density, temperature, and plasma current is investigated
through numerical simulation.
During the current quench (post-thermal) of a disrupting plasma, large
currents induced in the plasma halo, closing via poloidal flow through
conducting structures, can produce large, damaging forces on the vacuum
vessel and plasma-facing components. Predictive models are necessary to
evaluate these forces. An analytic model of the current quench,
consisting of a pair of ODE's in time for the core and halo currents, has
been shown to agree well with data from DIII-D; measurements of T_e and
Z_e\mkern-3mu f\mkern-3mu f in an experiment with massive injection of
He gas confirm that
post-thermal-quench resistivities are classical(D.A.~Humphreys
and D.G.~Whyte, Phys.~Plasmas 7), 4057 (2000)..
Here we develop a 1 amp; 1/2 D implementation of this model for use in our
transport code Corsica(http://wormhole.ucllnl.org/caltrans/); the
upgrade of the code to include modelling of current transport on the open
field-lines is in progress. We will apply the code to ITER-FEAT, and
various disruption-mitigation scenarios using high-pressure noble-gas
injection will be explored. Comparisons with the 0-D model will be presented.
A model is developed in order to describe the dynamics of
the magnetic island 'seeding’ process required for the
initiation of a neoclassical tearing mode in tokamak
plasmas. The formation of a magnetic island due to a
toroidally coupled magnetic perturbation is modeled as an
initial value problem. If differential rotation exists
between the two magnetic surfaces of interest, the dynamics
of the flow profile evolution also needs to be accounted
for. By extending the model beyond resistive MHD, the role
of two-fluid and neoclassical physics on magnetic island
formation can be addressed. In the presence of a fast
growing external magnetic perturbation and differential
rotation, the effect of the neoclassical polarization
mechanism on establishing a nonlinear island width threshold
is altered from cases appropriate for long resistive island
evolution timescales. In order to obtain a complete solution
to this problem in general, a neoclassical viscous force
that accounts for time dependent processes (time scales
faster than the ion collision time) needs to be developed.
Implications for neoclassical tearing mode dynamics in high
temperature plasmas will be discussed.
The plasma flow with positive ions and electrons propagates relative to
heavy negative ions of fullerenes in source of nanotubes. The flow
excites the solitary electric potential dip of large amplitude with
potential jump near the dip. The properties and evolution of this
excited perturbation are considered. The evolution equation is derived
for the case of any amplitude. It is shown that this perturbation of
large amplitude lead to acceleration of heavy negative ions of
fullerenes from region of their generation. One can use this electric
potential dip with potential jump near it for energy control of
fullerenes and rate optimization of nanotube generation.
1.W. Oohara, R. Hatakeyama, S. Ishiguro, and N. Sato: Proc. 1998 Int.
Cong. Plasma Physics, Praha, 22C (1998) 2419.
Complex plasmas are often used as a model system for solid-liquid-gas
phase
transitions. Usually, these transitions has been studied by melting the
plasma
crystal by lowering the neutral gas pressure. The lower gas pressure
enables instabilities to overcome frictional damping, thus heating the
particles and melting the crystal. However, lowering the pressure also
significantly alters the plasma environment which in turn effects the
particle
interaction potential.
Here, the initial stages of the crystallization of a 3D complex plasma
are
analyzed in a non-changing plasma environment (neutral gas pressure and
plasma
power constant). A 3D imaging method bas been developed in order to
analyze
the dynamics of crystallization in all three degrees of freedom
simultaneously.
The technique provides both the 3D particle position and 3D velocities
in the
viewed volume. The first empirical results for the time evolution of
the
particle temperature and microdynamics of the system will be
presented.
Recently, a number of colloidal plasma experiments,
in laboratory as well as
under microgravity conditions, have shown the
spontaneous development of voids.
A void is typically a small and stable centimeter-size
region (within the plasma) that is
completely free of dust particles and characterized
by sharp boundaries.
In the laboratory, the void is seen to develop
from a uniform dust cloud as a consequence of
an instability when the dust particle has grown
to a sufficient size.
We propose a nonlinear time-dependent model for void formation
in colloidal plasmas.
For experimentally relevant initial conditions,
the model describes the
nonlinear evolution of a zero-frequency
linear instability that grows rapidly in the
nonlinear regime and subsequently saturates
to form a void.
A number of features of the
model are shown to be consistent with experimental
observations under laboratory and microgravity
conditions.
Monodisperse dust grains have been levitated above a biased
conducting surface within a DC sheath in argon plasma. The
observed levitation heights and their dependence upon
surface bias voltage are near to values calculated from a
model. The ion charging current is calculated assuming that
the ions have a single energy determined by the sheath
potential profile and the electron charging current is found
assuming Maxwellian electrons. The grain charge is
calculated from the grain potential relative to the
potential in the surrounding sheath. The potential profiles
are found from both the Bohm collisionless model and
Riemann's collisional model. The potential profile is
different for graphite and steel surfaces suggesting that
secondary electrons are important.
A plasma crystal is a strongly-coupled dusty plasma, with
charged micron-size polymer spheres that arrange themselves
in a pattern, like a crystalline lattice. Here, we model
experiments with a 2D triangular lattice with hexagonal
symmetry. The particles interact through a Yukawa repulsion.
Linear compressional waves in this lattice obey a dispersion
relation(X. Wang et al., Phys. Rev. Lett. 86, 2569
(2001).) which is dispersionless for long wavelengths;
therefore, these waves can exhibit nonlinear effects such as
three-wave mixing and harmonic generation. In experiments,
waves are also damped by gas drag. Modeling the lattice as a
linear chain in the continuum limit, the particle velocity
v obeys a KdV-like equation, \frac\partial v\partial
t + \nu_d v = -v_p \frac\partial v\partial x
-\fracA2v \frac\partial v\partial x, where A
depends on \kappa which is the ratio of interparticle
distance and the Debye length, while v_p and \nu_d are
the wave phase velocity and the gas damping rate,
respectively. Beat waves and harmonics are produced, with a
threshold laser power determined by the damping level. It is
found that lattices with larger inter-particle separations
exhibit a stronger nonlinear interaction. Work supported by
NASA and DOE.
Experiments were performed to test our theoretical
predictions of three-wave mixing and harmonic generation of
compressional waves in a 2D plasma crystal. A 2D triangular
lattice with hexagonal symmetry was formed by levitating a
monolayer of particles in the sheath of a gas-discharge
plasma. The sheaths curvature provides a bowl-shaped
external confining potential. The particles were imaged
using a video camera, to record their motion. We excited
waves in the lattice using the radiation pressure of a sheet
of argon laser light. Waves propagated away from the narrow
excitation region. The amplitude of the wave excitation is
adjustable by varying the laser power. The wave damping is
determined by the gas pressure. We adjust the particle
spacing by varying the number of particles and the discharge
conditions. Particle motion was observed identifying
particles in each image and computing their velocities. We
excited waves at two frequencies, using two laser sheets.
The power spectrum of the waves is computed to identify beat
waves at the sum and difference frequencies, as well as
harmonics.
Molecular dynamics simulations were performed to study
three-wave mixing and harmonic generation of compressional
waves in a 2D plasma crystal. These simulations were used to
verify our analytic theory based on a KdV-like equation, and
to predict optimal experimental parameters, in preparation
for laboratory experiments using a dusty plasma. Using 5000
particles, which interact with a Yukawa potential and are
trapped by a parabolic external confining potential similar
to the bowl-shaped electrode sheath in the experiment, we
integrate the particles equation of motion for 60 seconds.
Applying a local external force, modulated in time to model
the radiation pressure force applied by a laser in the
experiment, sinusoidal compressional waves are excited.
Using two excitation regions at different frequencies,
mixing occurs at the sum and difference frequencies as well
as harmonic generation. We test the analytic theory’s
predictions of a threshold and of a spatial variation of
beat wave amplitude with distance from the excitation
region.
We report on analytical and simulation studies of
microphysical processes that trigger phase transitions in a
dusty plasma subject to ion streaming. For pressures below
the critical pressure Pc for condensation, the grains
acquire a large random kinetic energy and form a weakly
coupled fluid. If P is increased to greater than P_c,
the grains lose their kinetic energy and reach a strongly
coupled crystalline state. The dust heating in the fluid
phase is due to an ion-dust two-stream instability, which is
stabilized at P > P_c by the combined effect of
ion-neutral and dust-neutral collisions. If one starts from
the crystalline state and decreases the pressure to below
the critical pressure Pm for melting, transverse phonons are
destabilized by ion streaming, which destroys the short
range ordering of the dust grains and triggers melting. It
is found that P_m < P_c. For P_m < P <
P_c mixed phase states can exist.
*Supported by Office of Naval Research and NASA
A magnetically shielded, charge collecting rocket probe was
used on two flights of the MIDAS (MIddle Atmosphere Dynamics
and Structure) SOLSTICE (Studies of Layered STructures and
ICE) 2001 rocket campaign from Andoya, Norway. The probe was
a graphite collection surface with a permanent magnet
underneath to deflect electrons. The first launched June 17,
2001 was into a strong, multiply layered PMSE detected by
the ALWIN radar. The probe measured negative particles with
a peak charge number density of -1500 charges per cc. The
second (June 24), into another strong, multiply layered
PMSE, saw a band of positive particles centered in the
lowest radar echo maximum, and a negative particle layer
accompanied by a positive ion excess. The charge number
densities for the PMSE particles were several thousand
charges per cc. Unexpectedly, 2 km beneath the PMSE, the
probe also found a very pronounced negative layer which was
probably a noctilucent cloud. Computer simulations of
incoming, singly negatively charged ice aerosols were
performed using a rarefied flow field representative of the
MIDAS payload at zero angle of attack. Ice aerosols < 1 nm
in radius were diverted by the leading shock front,
indicating the smallest detectable ice aerosol by this probe
We consider some aspects of meteor physics. We focus on
several processes relevant to the interaction of meteoroids
with the atmosphere, that involve concepts typical of dusty
plasmas. The objective of our research is to simulate the
meteor flight directly using the kinetic PIC simulation code
DEMOCRITUS [1] and a new high accuracy PIC code designed to
simulate meteoroids in spherical geometry. The simulations
will investigate the physics determined by thermionic
emissions [2] and by the presence of potential wakes in the
meteor trail. These two aspects will be considered
particularly with respect to their relevance to
observations, such as the solution of still outstanding
problems in the interpretation of radar echoes from the head
and trail of meteors.
[1] G. Lapenta, Phys. Plasmas, 6, 1442 (1999).
[2] G. Sorasio, D.A. Mendis, M. Rosenberg, Planetary
Space Sci. , 49, 1257 (2001).
Recent investigations of dusty plasmas have shown that it
may be possible to use the trajectories of charged
microparticles to probe the electrical properties of a
microparticle cloud and the surrounding plasma environment.
In past experiments, self-generated dust particle ‘streams’
[E. Thomas, Jr., Phys. Plasmas, 8, 329 (2001)] have been
used as the source of probe particles. For the experiments
described here, two microparticle clouds are suspended in a
plasma. The clouds are separated by an array of small,
separately biased electrodes. Bias voltages applied to the
electrodes are used to control the flow of particles from
one cloud to the other. The particle image velocimetry (PIV)
technique is used to characterize the transport of
microparticles from one cloud to the other. Results are
presented on the interaction of the clouds as a function of
the bias voltage on different array elements. The
applicability of this technique as a diagnostic approach for
dusty plasmas will also be discussed.
Voids are regions within a dusty plasma in which there is a
complete absence of dust particles. The void boundary is
characterized by a very sharp gradient in the dust density.
Voids are a common feature of dusty plasmas formed under
microgravity conditions, but they can also be produced by
electrodes (probes) inserted into the dusty plasma. We
present results of a laboratory experiment designed to study
the formation of voids that are produced by biased probes
located within a dusty plasma. The experiment was performed
using the Auburn Dusty Plasma Experiment (DPX) which
generates a dusty plasma using a dc glow discharge in argon.
The voids are formed by inserting a small wire electrode
into the cloud. Measurements of the size of the void were
made for various bias voltages on the wire. The results will
be compared with a model in which a stable void is
maintained by balancing the outward electric force on the
negatively charged dust particles with the inward ion drag
force due to ions drawn by the probe.
The expansion rate dependence on pressure of the Electron Diffusion
Gauge (EDG) pure electron
plasma resulting from collisions with background neutral gas atoms is
analyzed. Expansion rate data is obtained for smaller
initial plasmas generated with
a smaller filament (outer diameter 1/4 of the wall diameter)
installed in the EDG device, and the data
is compared with previous results for larger-filament plasmas.
The measured expansion rate in the higher pressure regime is found to
be in agreement with the classical estimate
\[
\fracddt\langle r^2 \rangle =
\frac2 N_L e^2 \nu_enm ømega_c^2
\left(1+\frac2TN_L e^2\right).
\]
Progress on the fabrication and installation
of a standard on-axis parallel temperature diagnostic and a
phosphor-screen-based density imaging diagnostic is also presented.
The imaging diagnostic will include a grounded grid between the trap
and the 3kV-biased phosphor screen to minimize azimuthal shearing of
the plasma when large-amplitude m=1 diocotron modes are present.
These diagnostics will help clarify the behavior of the plasma
during the background-gas-induced expansion.
We present the first experimental results from a new Penning-Malmberg trap
using a 5\,Tesla magnetic field and a cryogenically cooled electrode structure
(T\sim5\,K) with the goal of producing cold (\Delta\epsilon\sim1\,meV),
high-density positron plasmas.
Positron bunches will be delivered in short bunches from a separate
accumulation trap that is fed by a radioactive source and a solid neon
moderator [1]. Using a 100\,mCi ^22Na positron source, filling rates of
10^10 e^+/h and plasma densities of 10^9\,cm^\mbox-3 are
expected. The positrons will thermalize to less than 10\,K by cyclotron
radiation. Radial compression is achieved by applying a
rotating electric field [2]. This trap is designed to be a nearly ideal
reservoir of
positron plasmas, with very long confinement and annihilation times. The trap
design, operation, its potential uses and first experimental results with
electron plasmas will be discussed.
[1] C.M. Surko, \textitet al., Non-Neutral
Plasma Physics III, J.J.\,Bollinger, \textitet al., eds., American
Institute of Physics (1999), pp. 3--12.
[2] R.G. Greaves and C.M. Surko, Phys. Plasmas, \textbf8, 1879 (2001).
There are a number of motivations to accumulate large
numbers of positrons [1]. We describe a multicell Penning-Malmberg trap
capable of confining \mboxN = 10^15 positrons, based on current
knowledge of cross-field transport of electrons in such traps. A novel
multicell design helps to minimize space charge limitations. Heating
associated
with plasma expansion is balanced by cyclotron cooling in a 10\,T field, and
long-term confinement is achieved using a "rotating wall" electric field
[2]. Confinement scaling and avoiding ionization on background gas place
important constraints on the plasma parameters:
\mboxn \sim 10^11\,\mboxcm^\mbox-3;\; \mboxT = 6\,\mboxeV;\;
\mboxN/cell \sim 10^10;\; \mboxL_\mboxp = 1\mboxcm;\; \mboxr_\mboxp = 1.5\,\mboxmm.
A trap for 10^15 positrons using 10\,kV potential wells requires
10^5 cells and occupies a volume 1\,m in
length by 0.5\,m in diameter. Applications, such as portable positron
sources will be discussed, as well as the research program required to
implement this design.
[1] R. G. Greaves and C. M. Surko, Phys. Plasmas, \textbf4, 1528 (1997).
[2] E. Hollmann, \textitet al., Phys. Plasmas, \textbf7, 2776 (2000).
Two-stream instabilities are studied analytically in the guiding center
kinetic regime, which is chosen in order that the results may be applied to
the mixing of antiprotons and positrons preceding antihydrogen recombination.
The guiding center kinetic description is valid for a range of
parameters which includes cases in which
magnetic fields are 3-5\,\rmT;
temperatures are 4-10\,\rmK;
positron densities are 10^7 - 10^8\,\rmcm^-3;
antiproton densities are 10^4 - 2\!\times\!10^7\,
\rmcm^-3;
the positron column radius is 0.05 - 0.3 wall radii;
and the antiproton column radius is 0.05 - 0.1 wall radii.
The
species occupy long,
cylindrical columns coaxial with an outer
conducting cylinder.
A constant, axial, externally generated magnetic field permeates the system.
Linear stability of the counter-streaming Maxwellian plasmas
is found as a function of
the species' temperature ratio, density ratio and
mean relative velocity.
Preliminary results for the effect of positron-positron collisions
on stability behavior are discussed.
We describe current experimental efforts to study shear modes and
measure heating rates in ion crystals confined in a Penning
trap. Up to 10^6 ^9Be^+ ions are laser-cooled to
less than 10 mK where they form a crystalline state. Previously,
the ion temperature was measured from the Doppler broadening of an
optical transition. Measurements below 10 mK were inaccurate due
to the 19 MHz natural linewidth of the transition. We will
summarize our progress on using a stimulated Raman transition
between two ground-state hyperfine levels to more accurately
measure the ion temperature. The width of this transition does
not depend on the linewidth of the excited state. Measurements of
the ion heating are motivated by the possibility of using the
Penning trap for making long-lived entangled and spin-squeezed
states of ions. We will also summarize our attempts to excite and
detect shear modes. Shear modes exist only in a crystalline (as
opposed to a liquid) plasma and provide a sensitive probe of the
ion correlations. As the lowest frequency modes of the system,
they could be an important factor in determining the usefulness
of the Penning trap for quantum information experiments.
In our studies of asymmetry-induced transport in a modified
Malmberg-Penning trap, a typical data set consists of the radial
flux \Gamma vs radius r for many values of the asymmetry
frequency ømega. For a given asymmetry frequency, the flux has a
complicated radial dependence, presumably because contributions from
diffusion, mobility, and resonant particle effects all depend on r
in different ways. To build an empirical model of this transport, we
would like to study each of these contributions in isolation.
According to the theory(D.L. Eggleston and T.M. O'Neil,
Phys. Plasmas 6, 2699 (1999).) both the mobility and the resonant
particle factor contain the quantity ømega - lømega_R, where
ømega_R(r) is the E\times B rotation frequency and l is the
azimuthal mode number of the asymmetry. In an
attempt to isolate the diffusive transport, we have thus selected
from our \Gamma vs r vs ømega data set those points where
ømega matches lømega_R. The resulting plots of \Gamma vs
density gradient \nabla n show a simple relationship which is
largely independent of center wire bias (as expected), but which
exhibits significant deviations from linearity. This may indicate
that other effects (e.g. radial temperature gradients) play an
important role in the transport.
In recent experiments
ultracold neutral plasmas were produced by photoionizing small
clouds of laser cooled atoms. This paper presents the results of molecular
dynamic simulations for the early time evolution of such plasmas. Contrary
to earlier speculation, no evidence of strong electron-electron
correlations is observed in the simulations even if
the initial value of the coupling parameter (\Gamma_e = e^2 / akT_e) is
much larger than unity.
As electron-electron correlations begin to develop,
the correlation energy is released to heat the electrons, raising the
electron temperature to the point where \Gamma_e \sim 1 and
limiting further development
of correlation. Further heating of the electrons occurs as a by-product of
three-body recombination.
When a model of laser cooling is added to the
simulation, the formation of strong ion-ion correlation is observed.
The rate of three-body
recombination is observed to be
in reasonable agreement with the traditional formula,
R = 3.9 \! \times \! 10^-9\:sec^-1
[n \; (cm^-3 )]^2 \; [ T_e (^\circ K)]^-9/2,
but care must be taken to use the correct temporally evolving
temperature, T_e.
The simulations are challenging because it is necessary to follow three-body
recombination into weakly bound (high n
quasi-classical) Rydberg states, and the time scale for such states is short
compared to that for the plasma dynamics.
Measurements of test-particle transport in pure ion plasmas
show 2D enhancement
over the 3D rates, limited by the
shear(C.F. Driscoll et al.),
Phys. Plasmas 9, 1905-1914 (2002).
in the E \times B
plasma rotation ømega_E. For finite plasma length L_p,
thermal particles may bounce axially many times before
rotational shear separates them in \theta.
This number of bounces
N_b \equiv ( \barv / 2 L_p) / (r \partial ømega_E / \partial r )
characterizes the approach to the 2D bounce-average regime.
For N_b < 1, test particle diffusion is due to long range
E \times B drift collisions with
impact parameters in the range r_c < \rho < \lambda_D.
Over the range 1 < N_b < 100, experiments measure
test particle diffusion increasing as N_b.
For exceedingly small shear N_b > 1000, we observe
transport rates consistent with the Taylor-McNamara estimate
for shear-free thermal plasmas.
Experimental data suggest the existence of convective
transport superimposed on diffusion, consistent with
the theory idea of transport due to large thermally excited vortices.
The two dimensional point vortex gas is a simple but useful
paradigm for more complex fluid and plasma flows.(D. Dubin
and D. Jin, Phys. Lett. A 284), 112 (2001).
This poster presents the theory of the collisional diffusion
and viscosity coefficients for a point vortex gas, in an applied
shear flow.
We show that the transport coefficients are reduced in the
presence of shear, just as for the shear reduction of transport
observed in fusion plasmas.
Here however, fluctuations are collisional rather than
turbulent, allowing a rigorous calculation of the
transport.
When there are several species of point vortices, we
find that Onsager relations require that the
diffusive flux conserves the total vorticity density
\rho (r) (proportional to charge density
in the plasma analogue).
Surprisingly, the diffusive flux concentrates
vortices with large positive
(or negative) circulations at maxima (or minima)
of \rho (r).
On a slower timescale, the momentum flux due to viscosity
drives the system to a global thermal equilibrium state.
Over the years, several conflicting theories have been put
forward to predict the final state of freely relaxing inviscid
2D turbulence in fluids and magnetized plasmas.
Theories based on minimizing enstrophy,
maximizing Boltzmann entropy,
maximizing fluid entropy, or maximizing the entropy
of a system with persistent vortices (yielding vortex crystal states)
all lead to different predictions for given values of the robust
invariants (the energy, angular momentum and circulation).
In order to explore the utility of these theories, we ran many
numerical vortex-in-cell (VIC) simulations, starting with unstable
initial conditions with the same values of the robust
invariants, but with different vorticity profiles.
Our results show that the robust invariants
by themselves are generally poor predictors of the
final relaxed state. We observe sensitive
dependence of the final state on initial conditions, thereby emphasizing
the importance of dynamics on relaxation.
Our findings suggest three general classifications of final states:
single central vortex, vortex crystal, and
minimum enstrophy.
In general, dynamics dominated by vorticity excesses (clumps)
lead to vortex crystals or a single central vortex;
whereas dynamics dominated by
vorticity deficits (holes) lead to minimum enstrophy-like final states.
We have observed diocotron wave echoes in magnetized
electron columns, demonstrating
the reversible nature of spatial Landau damping.
Here, two diocotron waves are externally excited
separated in time, and a third diocotron wave (the echo)
appears after the two applied waves have inviscidly damped
away.
Experimental images(J.H. Yu and C.F. Driscoll,
IEEE Trans. Plas. Sci. 30), 24-25 (2002).
show the damping as the spiral wind-up of the density
perturbation, and show the unwinding which results in the
echo. The diocotron wave phase mixing (and unmixing)
can be observed directly because the phase space
( \theta , p_\theta ) is equivalent to the configuration
space ( \theta , r^2 ).
Experiments agree with theory on the angular mode
number and appearance time of the echo.
The echo is surprisingly robust, occurring even though
end effects cause a v_z-dependence in the E \times B
rotation of each electron.
Only at late times does collisional velocity scattering
destroy the dynamical reversibility and diminish the echo.
We have identified the damping mechanism of a recently discovered
trapped-particle mode(A. A. Kabantsev et. al.),
Phys. Rev. Lett. 87, 5002 (2001). as velocity scattering in
a boundary layer near the separatrix.
This mechanism is similar to that
invoked earlier to describe the damping of the
dissipative trapped-ion
mode.( M. N. Rosenbluth et. al.), Nucl.
Fusion 12, 3 (1972).
The new mode is excited on a
nonneutral plasma column in which classes of trapped and passing
particles have been created by the application of an electrostatic
potential barrier.
Trapped particles on either side
of the barrier execute E \times B drift
oscillations that are 180^\circ out of phase, while passing
particles move along the field lines and Debye shield the
perturbed trapped-particle charge density.
A Fokker-Planck analysis focusing on
a thin boundary layer near the separatrix
yields a damping rate that scales as \sqrt\nu and is in good
agreement with measurements. In the experiments, the damping can
be enhanced by applying a weak potential that oscillates in
resonance with the bounce motion of the marginally trapped
particles, thus confirming that the damping is associated with
scattering across the separatrix. The theory is extended to
include the effect of this artificially enhanced scattering.
Measurements of trapped-particle modes in
pure electron plasmas have established
the mode damping as a function of magnetic field
and plasma temperature.
The modes propagate on plasma columns when
potential or magnetic field variations along the column cause local
particle trapping.
The modes consist of E \times B drifts of
trapped particles, partially shielded by axial flows
of untrapped particles.(A.A. Kabantsev et al.),
Phys. Rev. Lett. 87, 225002 (2001).
The damping occurs due to diffusion of particles
across the velocity-space separatrix between trapped
and untrapped fractions.(See poster by T.J. Hilsabeck
and T.M. O'Neil, this session.)
The measured damping rates are proportional to the number of
particles in a boundary layer near the separatrix; exhibit an
exponential decrease with temperature; and change magnetic
scaling from B^-1 to B^-0.5 depending on rigidity.
The damping is increased dramatically
when a RF-drive is applied in resonance with the bounce
motion of the marginally trapped particles,
enhancing their diffusion across the separatrix.
This diagnostic technique can ``map out'' the separatrix,
or determine the distribution function along it.
Spectra of thermal fluctuations in quiescent pure electron plasmas
have now been measured at Trivelpiece-Gould modes and at non-resonant
frequencies between modes.
Each weakly damped mode has time-averaged
electrostatic energy \textstyle \frac12 k_BT, where T
is intermediate between the plasma temperature T_p and the receiver
(load) temperature T_L.
Experimentally, the spectra determine T_p and T_L as well as
the internal and load-induced mode damping rates \gamma_p
and \gamma_L.
Away from a mode resonance, thermal fluctuations
of N particles with energy
N \cdot \textstyle \frac12 k_B T_p
are predicted to be reduced by Debye shielding
to a level \delta N \propto \sqrtN \; (\lambda_D / r_p )^3.
The spectrum between modes is thus most informative at high plasma
temperatures ( \lambda_D / r_p \geq 0.3 ) where the modes
are strongly damped ( \gamma_p / ømega \geq 10^-2 ).
Kabantsev et al.(A. A. Kabantsev, C. F.
Driscoll, T. J. Hilsabeck, T. M. O'Neil and J. H.Yu, in
Non-Neutral Plasma Physics IV), AIP Conference Proceedings
606, 2001, pp. 277-286 have reported experimental
observations and theory for trapped particle asymmetry modes
on cylindrical electron columns. In particular, the m=1;
k_z=odd mode exhibits strong damping from an unknown
mechanism that is conjectured by Kabantsev et al. to
be either diffusive mixing of trapped and untrapped
populations of particles or spatial Landau damping. We have
observed similar damping within a 3-dimensional
particle-in-cell simulation. The simulation model does not
include diffusive mixing. Spatial Landau damping is also
ruled out because the mode frequencies in the simulation
intersect the rotation frequency curve outside the plasma.
We describe efforts to isolate the mechanism of the damping.
The frequencies of the various plasma oscillation modes
(diocotron and Trivelpiece-Gould modes) in a non-neutral
electron plasma are dependent on both the plasma temperature
and on the plasma density profile. There have been
difficulties in calculating mode frequencies that match
those determined experimentally. We have experimentally
measured the frequencies of the diocotron and T-G modes as
well as the plasma density profile and temperature for
several plasma conditions. These frequencies are compared
with those obtained from kinetic simulations to determine
the conditions necessary for a consistent fit to all the
measured frequencies.
The spectrum of image charge fluctuations under an isolated
ring in a nonneutral plasma in a Malmberg-Penning trap
carries information about the velocity distribution function
of the plasma. We use this as a temperature diagnostic for
our plasma. We previously used a particle simulation to
derive the expected spectrum to compare with our experiment.
However, this was time consuming and cumbersome.
We have recently derived an analytic model for the expected
spectrum using randomly distributed noninteracting particles
that bounce between the two ends of the plasma. The
resulting power spectrum is a superposition of successively
wider and smaller versions of the velocity distribution. The
theory matches the results of the simulation with no
adjustable parameters. This means that with an absolute
calibration of our amplifiers we can not only derive the
temperature from this diagnostic, but also the total number
of particles in the plasma.
The long-range goal of the Penning Fusion eXperiment-Ions
(PFX-I) is the production of thermonuclear conditions by
means of spatial and/or temporal compression of a high
temperature, positive ion plasma. The present approach
involves the confinement of positive ions in a virtual
cathode produced by a non-thermal electron plasma held
within a Penning trap of modified geometry. Spatial
compression will be accomplished by shaping the virtual
cathode to provide focusing of ion orbits, while temporal
compression may be achieved by modulating the cathode
strength and hence parametrically driving the ion motions.
We will review data on the electron/ion plasma including the
electron energy distribution and evidence for ions trapped
in the virtual cathode. We will then present results from
initial attempts to tailor the shape of the virtual cathode
and to drive the ion motion by modulating the virtual
cathode strength.
The physics of non-neutral plasmas confined on magnetic
surfaces is fundamentally different from that in previously
studied configurations. We discuss the warm fluid
equilibrium equation for a pure electron plasma [T. S.
Pedersen and A. H. Boozer, PRL 88 (2002) p. 205002].
The equilibria are always minima of a suitably defined
energy; however, this energy may not be the free energy of
the system, so physical stability is not guaranteed by this
theorem. We present 2-D calculations of equilibria for
various boundary conditions, for both warm and cold plasmas
and discuss implications for transport and stability. The
basic physics of such plasmas can be addressed in the
Columbia Non-neutral Torus (CNT), a table-top ultrahigh
vacuum stellarator to be built at Columbia University. The
CNT experiment is being designed to provide significant and
variable magnetic shear, rotational transform, and magnetic
field strength. We will discuss the physics basis of the CNT
design and the basic physics capabilities of the experiment,
including its possible future use as a positron-electron
plasma trap.
The Columbia Non-neutral Torus (CNT) is a tabletop (R=0.3 m,
a=0.1 m, B=0.2 T) stellarator to be built at Columbia
University. The goal of CNT is to study the equilibrium,
stability, and transport of non-neutral plasmas confined on
closed magnetic surfaces. CNT will use four circular coils,
two interlocking coils with a variable tilt angle, plus two
additional poloidal field coils located above and below the
interlocking coils. By varying the angle between the
interlocking coils, the configuration can be varied
continuously from an aspect ratio of 2.4 with 33% shear to
an aspect ratio of 4.3 with a shear of –7%. CNT will be
designed to reach neutral pressures of 10^-10 Torr. The
electrons will be injected from a multi-sectioned tungsten
filament probe placed directly on the magnetic surfaces. The
bias voltage and current flowing through each section of the
filament can be varied to explore a variety of emission
profiles. The plasma will be diagnosed by numerous Langmuir
and sector probes, connected to a PCI-based data acquisition
and control system.
Two methods have recently been described for determining the
temperature of pure electron plasmas by measuring the
thermal fluctuation spectrum on a surrounding sector probe.
The first[1] employs the narrow resonant peaks associated
with Trivelpiece-Gould modes of the the plasma, and the
second[2] makes use of the broad continuous spectrum
associated with independent particle motion. We propose a
simple model, using the warm plasma dielectric function, for
calculating the fluctuation spectrum. It is valid for both
approaches and allows us to compare the two approaches. We
find that there is a broad low frequency spectrum in the
frequency range 0 < ohmega < kV, on which are
superimposed peaks, one associated with each mode. V is the
particle thermal velocity and k is the axial wave number.
The frequency of a mode is closely given by cold plasma
theory, but the height and width of a mode is the determined
by Landau damping, as shown in [1]. The broadband spectrum
associated with independent particle motion presented in [2]
is not, in general, correct since the particles are not
independent and correlation effects must be taken into
account. The modes are seen to emerge from the continuum as
their Landau damping decreases.
[1] Francois Anderegg, et al, CP606, Non-Neutral Plasma
Physics IV, AIP 2002, p253. [2] M. Takeshi Nakata, et al,
CP606, Non-Neutral Plasma Physics IV, AIP 2002, p 271.
Experimental and Theoretical Studies of Electrostatic
Confinement J. Park, R. A. Nebel, C. P. Munson, W. G.
Rellergert, M. D. Sekora Los Alamos National Laboratory
Previous theoretical work [R. A. Nebel, D. C. Barnes, Fusion
Technology (1998) and D. C. Barnes, R. A. Nebel, Phys.
Plasmas (1998)] suggested that an ion cloud confined by a
stable oscillating virtual cathode may undergo a
self=similar collapse producing periodic and simultaneous
attainment of high densities and temperatures. We are
currently conducting experiments to test the stability of
these virtual cathodes. Emissive probes have been used to
measure time and space resolved potential and electron
density profiles. Fluctuations in the plasma have been
measured by a passive receiver and a combination of an
external driver and a receiver. The observed virtual cathode
exhibits a bifurcation between states where the well depth
is ~ 60potential. The transition is a function of the injected
electron flux, grid biases, and the gas pressure.
Experimental results on fluctuation and stability of a
driven virtual cathode will be presented and compared with
theoretical predictions [R. A. Nebel, J. M. Finn, Phys.
Plasmas (2001)].
A truism of non-neutral plasma physics research is that
flat-top (i.e. n(r)=\hboxconst for r
Double well traps intended for the production of
anti-hydrogen must have regions of overlap between the
positrons and anti-protons. This overlap opens the
possibility of instabilities, and is similar to the
contamination of a single species column by a small number
of particles of opposite sign. In 1969, Levy, Daugherty and
Buneman predicted that such contamination could lead to a
surface instability, whch they named the ion resonance
instability. Previously, the l=1 instability had been
detected. New measurements detect the l=2 and l=3
instability. More importantly, the instability occurs in a
regime entirely different than that predicted by Levy et al.
Their instability was driven by shears created by mass
differences; here the instability is driven by shears
created by the difference in confinement regions for the
ions and electrons, and the different electric fields
therein.
The process of continuous electron injection into plasma
traps is investigated experimentally and with
Particle-in-Cell (PIC) simulations. Temporal measurements of
the trapped electron population and axially averaged
transverse density show unexpectedly rich dynamics. Similar
features are observed in PIC simulations. The number of
electrons in the trap increases over hundreds of axial
bounce times and exhibits distinct regimes of growth. The
population increases beyond that realized through
'ballistic' filling (which requires just two bounce times).
This increase is initiated by the development of a
two-stream interaction between electrons emitted from the
cathode and reflected electrons from the end-plug of the
trap. PIC simulations show that the axial phase space
distribution develops in a remarkable way: a series of
"bubbles" appear, which, as they oscillate, redistribute the
electrons in phase-space, increase the number of trapped
electrons and lead to a more uniform phase space density.
These bubbles have been observed experimentally. Very long
injection times exhibit signs of radial potential matching
of the plasma to the emitting cathode.
We will describe efforts to cool pure-electron plasmas using
inelastic collisions with a room temperature buffer gas. In
the initial experiments, a 1 eV gas of electrons confined in
a 1.5 kG Malmberg-Penning trap will be cooled using carbon
dioxide. CO2 was chosen for initial testing because of its
large ratio of inelastic to elastic scattering
cross-sections in the 1 eV range. If successful, this
cooling method could be used for rotating electric well
confinement techniques at low axial magnetic fields. It will
also be used to investigate rotating magnetic quadrupole
techniques.
With the recent advances in computer speed and memory,
three-dimensional (3d) computer codes have become practical
or nearly practical on single user workstations.
Two-dimensional (2d) codes have already proved very useful
in understanding problems in non-neutral plasmas. We will
report on progress towards an efficient 3d code tailored
towards problems in non-neutral plasmas. The electrostatic
particle-in-cell (PIC) code will use cylindrical coordinates
to match the typical trap boundaries, and we will begin by
implementing E\timesB dynamics perpendicular
to the external magnetic field and full dynamics along the
magnetic field. The code will be based on the 2d codes
developed by the Plasma Theory and Simulation Group at
Berkeley (see Verboncoeur et al., J. Comput. Phys. 104
(1993)). Once in operation, we will used the codes to
explore problems such as non-axisymmetric trapped two-stream
instabilities, and quadrupole induced resonant particle
transport.
We present nonlinear simulations of the low frequency
dynamics of electrons in a Malmberg-Penning trap, including
compressional and thermal effects [1,2].
First, we consider a 2D model where we assume the
effective plasma length constant in time. In this framework,
we further neglect the thermal effect on the velocity field,
and show with the PIC code KANDINSKY that Penning traps
could be used to perform geophysical fluid dynamics
experiments [3]. We also observe that, due to the presence
of the nonlinear m=1 instability, the initially hollow
density profile becomes peaked, as in the experiments.
Then, we show 2D results including thermal effects. In
this case, the development of the m=1 instability is
slowed since the equilibrium plasma length profile is closer
to the integrable profile, namely the length profile for
which there are no discrete unstable modes [4].
Finally, we present simulations of the 3D fluiddynamics
model of Ref. [2]. In particular, we investigate the
evolution of a m=1 perturbation for different electron
temperatures, when compressional and thermal effects are
included.
[1] J.M. Finn, D. del-Castillo-Negrete, D.C.
Barnes,\textitPhys. Plasmas, \textbf6, 3744, 1999.
[2] G.G.M. Coppa, A. D'Angola, G.L. Delzanno, G. Lapenta,
\textitPhys. Plasmas, \textbf8, 1133, 2001.
[3] G.L. Delzanno, J.M. Finn, G. Lapenta, "Nonlinear Phase
of the Compressional m=1 Diocotron Instability: Saturation
and Analogy with Geophysical Fluid Dynamics", submitted to
\textitPhys. Plasmas.
[4] G.L. Delzanno, V.I. Pariev, J.M. Finn, G. Lapenta,
"Stability Analysis of Hollow Electron Columns Including
Compression and Thermal Effects: Integrability Condition and
Numerical Simulations", submitted to \textitPhys. Plasmas.
Transport by cross-field diffusion has been studied in the
annular Penning trap in which a nonneutral plasma of
electrons is contained between concentric cylinders. At
densities sufficiently low (<10^5 cm^-3) to suppress
mobility transport arising from the space charge electric
field, the dominant sources of transport are diffusion from
collisions of electrons with added helium gas and asymmetry
transport from stray fields. The collisional diffusivity is
shown to scale linearly with collision frequency and
inversely with the square of the axial magnetic field. The
measured mean energy is initially 0.3 eV and the least
energetic electrons are lost more slowly as a consequence of
the energy dependence of the diffusivity. Decay constants
are about a factor of four higher than calculated from the
electron-helium momentum transfer collision frequency. Both
the asymmetry transport and the collisional transport are
shown to depend upon the cleanliness of the trap surfaces.
Issues of equilibrium, stability, and limitations on
confinement for toroidal electron plasmas are experimentally
addressed using the Lawrence Nonneutral Torus(M.R.
Stoneking \textitet al.,) Phys. Plasmas \textbf9, 766
(2002).. Electron densities in the range of 10^6
cm^-3 are trapped for up to 300 \mu s in a partially
toroidal trap (B=200G, R_o=43cm, a=5cm). A horizontal
electric field is required to provide equilibrium force
balance in the major radial direction. In this paper we
discuss experimental studies of the ion resonance
instability (due to ionization of background neutral gas)
and its effects on confinement. We assess the effects of
field asymmetry on confinement by independently applying a
vertical correction field and a field error. Initial results
using a new phosphor screen imaging detector are presented.
In addition, designs for an upgrade to the experiment are
presented. The upgrade will enhance the magnetic field by
\approx 5 times (to \approx 1 kG), improve vacuum
conditions (to 10^-9 Torr or better), improve field
symmetry and lower the aspect ratio. This work is supported
by U.S. Dept. of Energy and Lawrence University.
Electrostatic perturbations of the electron plasma in the
Malmberg-Penning trap ELTRAP have been investigated using
the cylindrical electrodes as probes, and a low noise
differential amplifier. The FFT exhibits a very high peak on
a noise spectrum. This frequency corresponds to a m=1
diocotron mode and remains constant for a time interval
which depends on the magnetic field, then decreases. The
variation is related to particle losses: at lower residual
gas pressure and higher B fields the oscillation is more
and more persistent. The amplitude of the oscillations grows
as long as the frequency remains constant, then saturates
(corresponding to plasma touching the walls) and decreases
with frequency. The mode amplitude grows in time following a
power law at low magnetic field (B<300 G) and
exponentially at higher fields. It is found that the
excitation of the mode occurs at the start of the hold phase
of the cycle, when the potential barrier is raised to
confine electrons. Measurements performed with increasing
rise time have shown that the growth rate decreases and at
long enough rise time the instability does not arise.
The optimal values of Q and \Delta, the detuning of a
microwave frequency from resonance, for cooling a pure
electron plasma with a microwave bath have been calculated.
An electron plasma which has no internal degree of freedom,
cannot be cooled down below a heat bath temperature.
However, the longitudinal cooling can be achieved by energy
transfer from the poorly cooled parallel degree of freedom
to the well cooled perpendicular degree of freedom. A
microwave tuned to a frequency below the gyrofrequency of
the electron forces an electron moving towards the microwave
to absorb a photon and then to move up one in Landau state.
The electron loses longitudinal energy in this process. On
the basis that most of the electrons are in the ground or
first excited state, we set up a transition equation and
develop a FEM code. With an appropriate condition for
B-field and intensity of the microwave, the cooling times
for several values of Q's and \Delta's are calculated and
the optimal values are found. Applying the optimal values at
appropriate times in a cooling process, the best cooling can
be obtained. For an electron plasma magnetized with 10T
B-field, cooling to the solid state can occur within 2
hours.
An experiment on structural dynamics at the ultra-fast time
scale in shocked metal samples is presented. The technique
development of an ultrafast x-ray diffractometer to generate
"molecular movies" is described. Preliminary results of
static x-ray measurements of thin unshocked Ga samples are
presented. Initial experiments use 200-300 mJ of a 100fs
Ti:Sapphire laser to excite K-alpha x-ray emission in an
aluminum wire. The x-ray emission is relayed using a
spherical crystal to the sample target. Plans for
experiments using Cu K-alpha emission will also be
described.
The ablation density is a critical quantity for good understanding and
stabilizing the Rayleigh-Taylor instability. However, ablation density
measurement has never been performed. High spatial resolution (<3 \mum)
hard x-ray (\sim5 keV) imaging technique is necessary to measure the
ablation density. We have developed Fresnel phase zone plate (FPZP) imaging
technique, which can image hard x rays with high spatial resolution. Using
4.7 keV x rays, we have obtained the FPZP spatial resolution of 2.2 \mum. We
performed the ablation density measurement experiment of the laser
irradiated polystyrene target. In this experiment, we coupled the flash
backlight technique with the FPZP imaging, and obtained high spatial and
temporal (\sim150 ps) resolution. We obtained density profiles of the
in-flight polystyrene target at different three timings. We compared the
measured density profile to the prediction of the 1-D hydrodynamic
simulation code.
Efficient, multi-keV x-ray sources are necessary for
radiography of high-density ICF fuel capsules. We present
calculations for the emission of K-shell Kr radiation
(h\nu\geq~13keV) from high-temperature, high-density
plasmas. The models include fine-structure energy levels and
complete manifolds of dielectronic recombination channels.
The collisional-radiative emission for transitions with
energies above 13~keV is computed with radiative transfer
through a 50~\mum plasma with the CRETIN code. Account is
taken of plasma temperature and density gradients as
predicted from LASNEX hydrodynamic simulations. Stark
broadening for the emitted line profiles is computed, as
well as source broadening and the instruemental resolution
effects. The observed total Kr K-shell radiative yield is
compared to both XSN-based and recent, detailed predictions.
The Kr K-shell is seen to be an efficient,
high-photon-energy radiator in recent experiments at the
OMEGA laser facility.
Radiative yields from high-Z ions are important in
understanding energy distributions and spectral
characteristics in plasmas. The understanding of x-ray
yields is important to the development of laboratory
radiation sources. Since these plasmas occur over a wide
range of plasma conditions, they requires a general non-LTE
population kinetics description. We investigate radiative
properties of non-LTE krypton plasmas with a
collisional-radiative (CR) model constructed with more than
80,000 levels covering more than 12 ionization stages. We
present the first detailed calculations of total radiative
cooling coefficients and the x-ray radiative cooling
coefficients of krypton ions as a function of electron
density above the coronal limit. Special attention has been
given to the process of dielectronic recombination.
Averaging schemes for level structures and configuration
populations have been investigated in order to produce a
more computationally tractable model. Radiative cooling
coefficients are given for plasma conditions from 600 eV
\leq T_e \leq 10~keV and 1\times10^14 \leq
N_e (cm^-3) \leq 1\times10^24. Ionic radiative
cooling coefficients as well as steady-state calculations of
the average charge state at given plasma conditions are also
presented.
Soft x-ray spectra from thin carbon layers heated by the
OMEGA and NIKE lasers have been obtained with both spherical
and planar targets, respectively, using a flat-field grazing
incidence spectrograph equipped with a gated microchannel
plate for temporal resolution. In both experiments,
late-time (recombining) hydrogenic C VI spectra show an
n-to-1 Lyman spectral series blending with the continuum at
n=4, contrary to n=9 in the n-to-2 Balmer series. It appears
unlikely that plasma inhomogeneities are the sole cause of
this anomaly, given the difference in the experimental
configurations. Other explanations for the line-to-continuum
merging (other than the usual Stark-broadened Inglis-Teller
effect) under consideration include non-thermal Doppler
broadening, deviations from statistical sublevel population
distributions, and opacity effects. Collisional-radiative
and hydrodynamic modeling, including cascades, is employed
to further understand this phenomenon.
X-ray diagnostics involving microchannel plates (MCPs) are
used for imaging and spectroscopy in laboratory simulations
of astrophysical systems and in many other types of
experiments. Modeling of the MCP and measurements of MCP
performance can be useful in optimizing these measurements.
Some early detailed modeling of MCP performance [Fraser,
Nucl.Instr. and Methods, 195 (1982)] was focused on pulse
counting applications. Present-day measurements often
involve the measurement of amplified signals; we discuss
modeling of this case. We focus specifically on the effect
on the signal of the distribution of depths and angles at
which the x-ray photons strike the channel walls. In
addition, we will show results from and the status of the
facility we have built at Michigan for testing MCPs and
x-ray framing cameras.
Non-uniformities in a thin high Z overcoat such as Au are a
potential contributor to the seed for Rayleigh-Taylor
instability.There are insufficient data on the spatial
structure distribution of thin Au film overcoats used in the
instability experiments for modeling. This may contribute to
the discrepancies observed between the modeling and the
experimental results where Au films with thickness less than
100 angstroms were used. In this presentation, we will
provide AFM analysis of thin Au films with averaged
thickness of 50 to 200 angstroms. Digital lineouts will be
included in the data set to be used directly for modeling.
We will present an overview of techniques used to fabricate
and characterize targets used in hydrodynamics and equation
of state experiments for HEDP research. Planar targets made
at Schafer Laboratories are used for experiments on NRL’s
Nike KrF laser, the Omega laser at The University of
Rochester’s Laboratory for Laser Energetics, and other
drivers. Recent experiments have demanded increasing target
complexity. Targets for EOS experiments may have several
layers of material including Kapton, micromachined aluminum
flats or steps, and witness plates consisting of glass
supports, thin polyimide covers, and aluminum stripes.
Targets for hydrodynamics experiments consist of various
densities of material with patterned surfaces, and metallic
coatings. We will present our present capabilities for these
kinds of targets and what we foresee as the next generation
of plastic and foam targets. This work is supported by the
U.S. Department of Energy under contract DE-AC03-01SF22260.
K-shell emission spectroscopy is commonly used to diagnose
core temperature and density of Ar-doped ICF implosions at
OMEGA and Z. To investigate details of spectra formation, we
perform simulations of Ar-doped indirect laser-driven
implosions and generate synthetic spectra and plasma core
images observable at the collapse of the implosion. VisRad
is a user-friendly view factor code used to simulate the
radiation environment in three-dimensional objects. It
predicts temperature and radiative flux distributions
throughout target components in high-power laser and z-pinch
laboratory plasma experiments. Those time-dependent hohlraum
radiation temperatures and fluxes are used to initialize
target implosion simulation with a 1D rad-hydro code BUCKY.
Plasma core temperature and density distributions from the
hydro code are then used to compute Ar emission spectra and
core images. To this end we utilize multi-dimensional
collisional-radiative, spectral analysis code SPECT3D. We
will discuss details of the calculations and compare our
results against experimental data.
With the incorporation of full Coulomb electron broadening models
into our Stark spectral line broadening code MERL, we have been able
to successfully predict experimentally observed spectral line shifts in K-
and L-shell argon spectra emitted from ICF microballoon implosions reaching
electron densities on the order of 1-3\times 10^24/cm^3. We have
also looked at
the possible effects of these shifts on spectral line merging as electron
density increases. We will now focus on asymmetries in these line spectra
with a concentration on the line wings. The two full Coulomb electron-
broadening models used in our line spectra code are currently predicting
different amounts of red/blue wing asymmetry that we will scrutinize in
greater detail. We have also successfully incorporated the ion quadrupole
effect into the calculation of these spectra and will look at its effect
on this asymmetry as well as its effect on the merging of these line
spectra as electron density increases. Finally, we will use these
theoretical spectra to analyze experimental data from upcoming ICF implosion
shots on the OMEGA laser system of microballoons containing deuterium and
small amounts of argon.
This paper describes some improvements to the numerical
efficiency of the three-dimensional radiation hydrodynamics
code FastRad3D. FastRad3D is a compressible hydrodynamics
code containing most of the physical effects relevant for
the simulation of high-temperature plasmas including
inertial confinement fusion (ICF)-regime Rayleigh-Taylor
unstable direct drive laser targets. These effects include
inverse bremmstrahlung laser energy absorption, classical
flux-limited Spitzer thermal conduction, real (table
look-up) equation-of-state with either separate or identical
electron and ion temperatures, multi-group variable
Eddington radiation transport, and multi-group alpha
particle transport and thermonuclear burn. FastRad3D uses an
MPI message-passing model to obtain parallelism on
workstation clusters and supercomputers. We discuss
improvements to the temperature solver and to the transport
algorithm during the burn phase of the calculation. The
latter employs the BIC algorithm treating the pressures
implicitly and other transport variables explicitly to
eliminate the sound speed limitations on the time step size.
A sample calculation with timings on various computer
architectures will be shown
Since 1992, the All-Russian Scientific Research Institute of
Experimental Physics (VNIIEF) and the Los Alamos National
Laboratory (LANL), the institutes that designed the first
nuclear weapons of the Soviet Union and the United States,
respectively, have been working together in fundamental
research related to pulsed power and high energy density
science. Experimental and theoretical work has been
performed at VNIIEF and LANL in areas as diverse as
imploding z-pinch liner physics and applications, fusion
plasma formation, isentropic compression of noble gases, and
explosively driven high current generation technology [1].
Recent joint work has focused on the Atlas capacitor bank
(23 MJ, 30 MA, 6 microsec) now operational at LANL. Even
before Atlas became operational, VNIIEF's magnetic flux
compression capability was used to provide the US with the
first available data at ATLAS' upper performance limit (31
MA, 4 microsec, 12 km/s velocity for 50 g liner mass).
VNIIEF has recently designed and fielded imploding liner
experiments on Atlas, with the goal of studying material
strength properties by observing instability growth. The
collaboration is reviewed and new results are reported.
[1] "US/Russian Collaboration in High-Energy-Density Physics
Using High-Explosive Pulsed Power: Ultrahigh Current
Generation, Ultrahigh Magnetic Field Applications, and
Progress Towards Controlled Thermonuclear Fusion," I.
Lindemuth et al., IEEE Trans. Plas. Sci. 25, 1357 (1997).
Direct confinement of high-beta plasma by material walls
appears an attractive option for fusion (MTF) but has been
studied only a little. The well-benchmarked 2-D rad-MHD code
MHRDR is being used to design an inverse z-pinch experiment,
driven by the 2-TW Zebra generator, to study MTF transport
and confinement. According to MHRDR, the plasma is expected
to evolve into a near-equilibrium, with thin wall sheaths
that contain steep temperature and density gradients. The
plasma should take about 3 microseconds to cool, even in the
presence of considerable convection. This is much longer
than if free-streaming losses of ions or
unmagnetized-electron conduction losses were present. This
would make MTF attractive, if borne out by experiment. A
parametric study of the inverse pinch, as a function of
chamber geometry, chamber dimensions, seed magnetic field,
and initial gas pressure, is helping to design the
experiment. Modeling has found a region of parameter space
with adequate heating, formation of a quasi-static magnetic
equilibrium, and near-classical cooling rate, even in
presence of substantial plasma convection. Experimental
verification of the energy transport in this simple
wall-confined plasma would increase confidence in the design
of integrated liner-on-plasma experiments.
Induced Spatial Incoherence (ISI) is an effective technique
for achieving the high degree of spatial illumination
uniformity required for direct-drive fusion. Although ISI
provides ultrasmooth illumination at the far-field of the
laser, where the target is located, it may still allow the
beams in the quasi near-field to develop significant
time-averaged spatial nonuniformities. This structure, which
arises primarily from random phase distortion and Fresnel
diffraction, increases as the beams propagate away from the
pupil plane images located at the amplifiers; it is distinct
from any structure imposed by amplifier gain
nonuniformities. Because of the spatial incoherence of ISI
beams, the time-integrated structure is significantly
smaller than that experienced by coherent beams.
Nevertheless, it remains a potential optical damage issue,
especially in the long delay paths required for large
angularly-multiplexed KrF lasers. This presentation compares
simulations and measurements of quasi near-field structure
in the Nike KrF laser, and presents simulations showing how
optical relaying can control the problem in a future KrF
driver.
The rep-rated KrF laser system Electra is one component of
the High Average Power Laser Program. A simulation code,
Orestes, has been developed to support experiments on the
Electra gas laser amplifier, to improve efficiency, and to
scale to larger systems such as the Integrated Research
Experiment (IRE). Orestes is a first principles physics code
which includes e-beam ionization and excitation, plasma
chemical kinetics with 1-D spatial resolution along the
lasing axis, detailed vibrational structure of the KrF
molecule, transport of lasing photons, and time-dependent
transport of amplified spontaneous emission in 3-D with line
narrowing. Validation of the code is based on comparison
with high powered laser experiments. Predictions for the
laser output from Electra both as an amplifier and an
oscillator are presented as a function of total pressure and
composition. These figures indicate the impact of 3-body
relaxation on the predicted laser output and specify the
optimal conditions. Initial studies of the configuration and
yield for the IRE will also be discussed.
Electra is a repetitively pulsed, electron beam pumped
krypton fluoride (KrF) laser that will develop the
technologies that can meet the Inertial Fusion Energy (IFE)
requirements for durability, efficiency, and cost. The
Electra laser is pumped with two opposing electron beams
each with parameters of 500 kV, 90 kA, with a 100 ns
flat-top pulse duration, and a cathode area of 27 x 97
cm^2. The e-beam propagates through a hibachi structure,
which supports a thin foil that isolates the vacuum diode
from the high-pressure (>1 atm) laser gas. It has been
demonstrated that segmenting the beam into strips to miss
the hibachi support ribs significantly increases the
electron beam deposition efficiency. The energy deposition
efficiency is defined as the ratio of energy deposited in
the laser gas over the vacuum diode e-beam energy. Energy
deposition efficiencies of 75have been achieved with a 500 keV e-beam. In addition, 1-D
and 3-D codes have simulated the e-beam propagation through
the hibachi, and 1-D codes predict a maximum energy
deposition efficiency of 81
The common knowledge of Hermite/Laguerre mode conversion can
introduce a new aspect into the research of
ultra-short-pulse laser plasma interaction. Among several
methods for the mode conversion, we adopted a spiral phase
plate with the first order topological (azimuthal) charge
that generates not only an intense optical vortex but also
the first order Bessel beam with using a phase element like
an axicon lens. In addition the conversion of polarization
state is also interesting. A beam with radial polarization
has a longitudinal electric field near a focus. We developed
a liquid crystal device that uses the space-variant optical
rotatory. This device can efficiently generate the axially
symmetric (radial and azimuthal) polarization from the usual
linear polarization. We will report in detail the
fabrication processes of these optical elements, phase and
polarization properties of mode-converted beams and the
measured longitudinal electric field distribution.
In the laser-plasma interaction, the motion of electron
depends on spatial variations of the polarization and the
phase of incident laser beam. We developed special optical
elements (a spiral phase plate and a liquid crystal
polarization rotator) for generating the axially symmetric
(radial or azimuthal) polarization and the optical vortex
(Laguerre-Gaussian beam) with linear or circular
polarization. These optics were installed into a Ti:sapphire
laser system (T^6 laser) that deliver ~100mJ/100fs at
800-nm wavelength. We will present density profile, induced
magnetic field (both measured using UV probe beam
synchronized to an interaction beam), energy spectra of
forward accelerated electrons and their dependence on the
spatial variation of phase and/or polarization.
The response of candidate Inertial Fusion Energy first wall
materials to the intense bursts of x-rays and ions that will
emanate from IFE targets is an important issue for power
plants and for any facility that would test high yield
target performance. In an effort to gain understanding of
the behavior of these materials while undergoing rapid phase
changes and to validate code that predict such behaviors, a
multi-institution group has been conducting experiments on
the Z and RHEPP facilities at Sandia. As part of this
project, calculations of irradiation with tungsten wire
array x-ray on Z and ions on RHEPP have been performed with
the BUCKY computer code. When comparing experiments to
calculations for graphite and tungsten samples, we have
found some behavior that is not predicted by the code. We
will show how the greater than 1 keV lines in the Z tungsten
wire array x-ray source affect the material response. On the
RHEPP ion experiments, we will show how sensitive the
results are to the thermal conductivity of the material.
We are investigating the response of candidate Inertial
Fusion Energy (IFE) reactor materials to pulsed x-rays (on
Z) and energetic ions (on RHEPP) at fluences similar to
those predicted for future reactors. Both the Z and RHEPP
facilities are located at Sandia National Laboratories.
Primary dry wall armor materials under consideration are
carbon and tungsten in various forms, in either flat or
'engineered' geometry such as carbon 'velvet'. Experiments
are underway to 1) determine single-shot threshold for
ablation, 2) characterize surface roughening occurring below
this ablation threshold, and 3) measure net ablation for
doses exceeding the ablation threshold, as a function of
dose. Graphite is observed to ablate readily above a
threshold dose level of 3-4 J/cm^2. Sintered graphite
and tungsten sheet are observed to exhibit thermomechanical
responses that result in material loss beyond that expected
from sublimation predicted by BUCKY and other modeling
codes. Experiments are planned to measure erosion of the
carbon velvet tips and shafts due to RHEPP ion exposure, to
measure directly the time-dependent surface temperature
during ion beam exposure, and to compare both with code
predictions.
One dimensional radiative hydrodynamic simulations of the
response of gas protected dry wall chambers to the output of
high gain laser direct drive targets are presented. It is
found that the dominant threat is from the ionic component
of the target output. Variations in chamber operating
temperature, radius, target yield and buffer gas composition
are considered, and a variety of options satisfying both the
constraints of per-shot chamber wall degradation and target
injection are presented. Satisfying these constraints is
necessary, but nor sufficient to assure a successful chamber
design. The amount of implantation of high energy burn
products into the wall for each of the variations consiered
will be discussed.
Afterglow stage of plasma/gas temporal evolution in the ife
chamber plays very important role both for protection of the
chamber first wall from plasma impact damage and for
favorable conditions of next pellet injection which will
follow in a time scale ~0.1s [1]. In this report we analyze
main physics processes leading to residual gas/plasma
cooling and plasma recombination. We develop a time
dependent numerical model to study the effects of large
convective cells, plasma/gas radiation opacity on cooling
and recombination processes. We discuss the impact of
residual plasma and radiation field on the heat flux to the
target. [1] S. I. Krasheninnikov, "IFE Dry Wall Chamber
Physics Issues", 29th EPS Conference on Plasma Physics and
Controlled Fusion, 17-21 June 2002, Montreux, Switzerland
Plasma forming from metal surfaces in high power pulsed
vacuum discharges limits the power transmitted to a load
through magnetically insulated transmission lines, and
eventually shunts the load, producing so-called MITL
closure. An experimental investigation of the plasma
formation and evolution is being developed with the goal of
understanding and controlling the explosive electron
emission, the plasma closure, which depend on the electrode
conditioning and on the electric and magnetic field
strength. Cylindrical coaxial electrode systems are driven
by the 2 MV, 2 ohm Zebra generator, that produces load
currents rising to 1 MA in 100 ns. The current flowing
through the system is measured in detail with B?dot probes
located before and after the MITL section. Faraday cups and
radiochromic film are used to measure electron beams. To
characterize the plasma produced in the anode-cathode gap,
time-resolved imaging and spectroscopy, and laser
diagnostics are being developed. The electrode initial
conditions are carefully characterized and controlled.
Preliminary experiments with a short circuit load showed
that the plasma closure can be predictably controlled by
changes in geometry, via the electric and magnetic fields.
Computer simulations of the plasma formation and evolution
in these experiments will be performed.
The hot, dense plasma produced in plasma focus is a rich
source of phenomena such as the emission of intense
radiation, neutron yield, as well as copious nuclear fusion
products. One of the most important characteristics of the
plasma focus is intensive neutron emission that is produced
when deuterium is used as filling gas. There are a lot of
experimental parameters required for optimizing neutron
yield, such as length of center electrode, radii
of electrodes, gas pressure, impurities, insulator
material, geometry and so on. However, the optimum
condition for each device is roughly speaking, obtained by
pinching the plasma in front of the anode at the phase near
the current maximum. When a strong focus occurs, the
impedance of the pinch region increases dramatically, and
the circuit energy is concentrated there. In order to
increase the input energy on the pinch phase, the energy
dissipation and energy loss in run-down phase of discharge
should be small. In this paper, the influence of the cathode
structure on production of neutron yield in a 7 kJ
Mather-type plasma focus device have been investigated by
using two types of cathode electrode, 1) bar and 2) tubular
cathodes. In the present experimental results that
were obtained under the same conditions except for the
cathode structure, the energy dissipation in the run-down
phase was much lower in the bar cathode than in the tubular
one and as a result, the neutron yield was higher in the
bar cathode. The experimental results obtained by many
authors using both cathodes do not seem to support our
experimental results. However, they were obtained in
different devices with the bar or tubular cathode. The
present result clearly shows that for a complete comparison
it is necessary to investigate both types of cathode
in the same device under the same optimum conditions
Plasma foci are well know to be efficient neutron
generators, with a great potential for immediate
applications. For this purpose, it is particularly important
to assess the uniformity of their behaviour, which strongly
depends on the geometry details and the materials used in
their construction. It has been established that there are
competing mechanisms in the neutron generation, that yield
both isotropic and anisotropic components. However, the
latter, which may be associated to the generation of axial
ion-beams has been found to contribute no more than 30the total neutron yield, and less than 10particular device. As a matter of fact, measurements of the
ratio of head-on and side-on neutron fluxes have been found
to be grossly misleading, since they may be extremely large
due to very pronounced anisotropic components, even though
they may actually contribute less than 10neutron yield. The isotropic component, on the other hand,
can be reasonably described by thermonuclear models, and
within the experimental error, allowed by the regularity of
the device behaviour, can be properly characterised by
side-on measurements. The purpose of this work is to study
the regularity of the neutron emissions from a small dense
plasma focus (5kJ at 37kV) [1], analysing the time of flight
signals from three, side-on, on-line, scintillation
detectors.
[1] F. Castillo, J.J.E. Herrera, J. Rangel, A. Alfaro, M.A.
Maza, V. Sakaguchi, G. Espinosa and J.I. Golzarri, "Neutron
Anisotropy and X-ray Production of the FN-II Dense Plasma
Focus", Brazilian J. Phys. Vol.32 (2002) 3-12.
[FP1.040] Penetration of AC Fields into a Reversed Field Pinch in Oscillating Field Current Drive
K. J. McCollam, J. K. Anderson, A. P. Blair, D. Craig, D. J. Den Hartog, F. Ebrahimi, G. Fiksel, C. B. Forest, P. D. Nonn, S. C. Prager, J. C. Reardon, J. S. Sarff (University of Wisconsin), W. X. Ding (UCLA)
[FP1.041] Pellet Injection into MST RFP Plasmas
M.D. Wyman, B.E. Chapman, D. Craig, D.A. Ennis, R. O'Connell, S.P. Oliva, S.C. Prager, J.C. Reardon, J.S. Sarff (UW-Madison), S.K. Combs, L.R. Baylor, D.T. Fehling, P.W. Fisher, C.R. Foust, D.A. Rasmussen, J.B. Wilgen (ORNL), D.L. Brower, W.X. Ding (UCLA)
[FP1.042] Spectral Motional Stark Effect Measurements in MST
D. Craig, J.K. Anderson, A.P. Blair, B.E. Chapman, D.J. Den Hartog, E.A. Den Hartog, G. Fiksel, C.B. Forest, K.C. McCollam, J.S. Sarff (University of Wisconsin - Madison, USA), A. Lizunov (Budker Institute for Nuclear Physics, Russia)
[FP1.043] Heavy ion beam probe measurements of the equilibrium potential and electrostatic fluctuation profiles on the Madison Symmetric Torus
K.A. Connor, J. Lei, P.M. Schoch, D.R. Demers, U. Shah, J.G. Schatz (Rensselaer Polytechnic Institute, Troy, NY 12180), MST Collaboration
[FP1.044] Density Fluctuation Measurements in the MST Reversed Field Pinch Using a Heavy Ion Beam Probe
X. Zhang, K.A. Connor, D.R. Demers, J.G. Schatz, P.M. Schoch (Rensselaer Polytechnic Institute, Troy, NY)
[FP1.045] Core Magnetic Fluctuations and Current Profile Dynamics in the MST Reversed-Field Pinch
W.X. Ding, D.L. Brower, S.D. Terry (Electrical Engineering Department, University of California, Los Angeles), J.K. Anderson, T.M. Biewer, D. Craig, C.B. Forest, J.S. Sarff, C. Sovinec, S.C. Prager (Physics Department, University of Wisconsin-Madison)
[FP1.046] SXR imaging of chaos healing in the core of the Madison Symmetric Torus (MST) RFP
P. Martin (1), P. Franz (1), B.E. Chapman (2), D. Craig (2), L. Marrelli (1), P. Piovesan (1), S.C. Prager (2), I. Predebon (1), J.S. Sarff (2), G. Spizzo (1), C. Xiao (3), R.B. White (4) ((1)Consorzio RFX-Associazione Euratom-Enea sulla fusione,Padova, Italy (2)Physics Department, University of Wisconsin, Madison, WI (3)Department of Physics and Engineering Physics, University of Saskatchewan, Saskatoon, Canada (4)PPPL, Princeton, NJ)
[FP1.047] Effects of fast particles on internal modes in reversed field pinches
Vladimir Svidzinski, Stewart Prager (University of Wisconsin-Madison)
[FP1.048] Impurity ion measurements on MST
D.A. Ennis, D. Craig, D.J. Den Hartog, G. Fiksel, D.J. Holly (University of Wisconsin-Madison)
[FP1.049] measurements of m=0 excitation and nonlinear coupling in MST
seung-ho choi (first author), darren craig, stewart prager (Affiliation)
[FP1.050] Technique development of spectroscopic ion beam imaging for mapping magnetic fields in a plasma
D.R. Demers, K.A. Connor, P.M. Schoch, R.J. Radke (Rensselaer Polytechnic Institute, Troy, NY 12180), J.K. Anderson, D. Craig, D.J. Den Hartog (University of Wisconsin, Madison, WI 53706)
[FP1.051] Current Transport Simulations of the MST RFP with a Tearing-mode Based Hyper-resistive Coefficient.
L.D. Pearlstein, R.A. Jong, L.L. LoDestro (LLNL), H.L. Berk (IFS, UT Austin.)
[FP1.052] Single and Multihelical States in Reversed Field Pinches
Richard Nebel, Charles Bathke, John Finn (Los Alamos National Laboratory)
[FP1.053] Current profile control experiments in EXTRAP T2R
P. Brunsell(1), M. Cecconello(1), J. Drake(1), P. Franz(2), J.A. Malmberg(1), L. Marrelli(2), P. Martin(2), G. Spizzo(2) ((1) Alfven Laboratory, Royal Institute of Technology, Association EURATOM-NFR, Stockholm, Sweden (2) Consorzio RFX, Associazione EURATOM-ENEA sulla Fusione, Padova, Italy)
[FP1.054] Numerical analysis of magnetic topology in the Reversed Field Pinch
I. Predebon (1), R.B. White (2), L. Marrelli (1), P. Martin ((1) Consorzio RFX, Associazione Euratom-Enea sulla fusione, Padova, Italy (2) Princeton Plasma Physics Laboratory, Princeton NJ)
[FP1.055] Controling MHD mode dynamics in an RFP with rotating helical field
Sadao MASAMUNE, Taketo YAMAMOTO, Katsumi OHTA, Motomi IIDA (Kyoto Institute of Technology, Sakyo-ku, Kyoto 606-8585, Japan)
[FP1.056] Effect of multiple resistive shells on the dynamics of the slinky mode in RFP plasmas
S. C. Guo (Consorzio RFX, Associazione Euratom ENEA sulla Fusione,Italy), M. S. Chu (General Atomics)
[FP1.057] Nonlinear Resistive MHD Computations of PPCD and Cross Section Shaping in the RFP
J. M. Reynolds, C. R. Sovinec (University of Wisconsin-Madison)
[FP1.058] MHD Invariants in Turbulent Dynamo: Effect on Random-Phase Approximation and Choice of Basis Functions
Leaf Turner (Theoretical Division, Los Alamos National Laboratory)
[FP1.059] MHD nonlinear behaviour and dynamo in numerical simulations of the reversed field pinch with external drive of toroidal magnetic flux (PPCD).
Susanna Cappello (Consorzio RFX, Associazione EURATOM-ENEA sulla fusione, CNR, Padova, Italy.)
[FP1.060] MHD Phenomena
[FP1.061] Local equilibrium of plasmas
Allen H. Boozer (Columbia University, New York, NY 10027)
[FP1.062] Simulation studies on nonlinear coupling of m/n=1/1 and 2/1 tearing modes in high-beta tokamak plasmas.
S. TSURIMAKI, S. HAMAGUCHI, M. WAKATANI (Graduate School of Energy Science, Kyoto University)
[FP1.063] Free boundary and Profile effects on the n=1,m=1 MHD instability
Janardhan Manickam (Princeton Plasma Physics Laboratory)
[FP1.064] Nonlinear evolution of the resistive m=n=1 MHD internal mode
Marie-Christine FIRPO, Bruno COPPI, Linda SUGIYAMA (Massachusetts Institute of Technology)
[FP1.065] Two-Fluid Effect on Non-Linear Kink Instability in Cylindrical Tokamak with Negative Central Current
Akihiro Ishizawa, Masahiko Sato, Masahiro Wakatani (Graduate School of Energy Science, Kyoto University)
[FP1.066] Integrated Predictive Simulations of Sawtooth Oscillations
Canh N.~Nguyen, G. Bateman, A. Kritz (Lehigh University), Franco Porcelli (Politecnico di Torino)
[FP1.067] Extended MHD Simulations of Stellarators and Tokamaks with M3D
H.R. Strauss (NYU), G.Y. Fu, W. Park, J. Breslau, A. Pletzer, S. Jardin (PPPL), L.E. Sugiyama (MIT)
[FP1.068] Hybrid Simulations of Energetic Particle-driven MHD Mode in Toroidal Plasmas with M3D
G.Y. Fu, J. Breslau, J. Chen, S. Jardin, W. Park (PPPL), H.R. Strauss (NYU), L.E. Sugiyama (MIT)
[FP1.069] Two-Fluid Effects on Nonlinear Steady States in Stellarators*
L.E. Sugiyama (MIT), H.R. Strauss (NYU), W. Park (PPPL)
[FP1.070] NIMROD Simulations of Classical Tearing Modes
S.E. Kruger, D.D. Schnack (SAIC)
[FP1.071] Alfvén Waves in Gyrokinetic Plasmas
W. W. LEE, H. Qin, J. L. V. LEWANDOWSKI (Princeton Plasma Physics Laboratory, Princeton, NJ 08543)
[FP1.072] Study of Thermonuclear Alfvén Instabilities in Next Step Burning Plasma Experiments^1
N.~N. Gorelenkov, R. Budny, C.~Z. Cheng, G.-Y. Fu, G. Kramer, R. Nazikian, D. Meade (Princeton Plasma Physics Laboratory), H.~L. Berk (IFS, Austin, Texas), W.~W. Heidbrink (University of California, Irvine, California 92697)
[FP1.073] Excitation of Toroidicity-Induced Alfvén Eigenmodes using Electrodes in a Heliotron/Torsatron Plasma
Go Matsunaga (Department of Energy Engineering and Science, Nagoya University), Kazuo Toi, Chihiro Suzuki, Keisuke Matsuoka (National Institute for Fusion Science), CHS Team
[FP1.074] Nonlinear Behavior of Pressure Driven Mode in a Heliotron Plasma with a Vacuum Magnetic Island
Takeshi Unemura, Masahiro Wakatani (Graduate School of Energy Science, Kyoto University)
[FP1.075] Computation of Singular MHD Instabilities with DCON
A.H. Glasser (Los Alamos National Laboratory)
[FP1.076] AEST: Adaptive Eigenvalue Stability Code
L.-J. Zheng, M. Kotschenreuther, F. Waelbroeck, J. W. Van Dam, H. Berk (Institute for Fusion Studies, University of Texas at Austin)
[FP1.077] A Computational Approach to the Hazeltine-Mahajan Two-Fluid Equations
J. C. Wiley, P. M. Valanju (Univ. of Texas at Austin)
[FP1.078] MHD-like equations for electromagnetic kinetic simulations
H. Vernon Wong (Institute For Fusion Studies, University of Texas at Austin)
[FP1.079] Axisymmetric MHD Equilibria with Arbitrary Flow and Applications to NSTX
T.A. Gardiner, L. Guazzotto, R. Betti (Laboratory for Laser Energetics, U. of Rochester), J. Manickam (Princeton Plasma Physics Laboratory)
[FP1.080] Equilibrium and Stability of Flowing Two-fluid Plasmas
Hideaki Yamada (Kyoto Univ.), Takayuki Katano, Kazumi Kanai, Akio Ishida (Niigata Univ.), Loren Steinhauer (Univ. Washington)
[FP1.081] Toroidal flow stabilization of Disruptions in High \beta Tokamaks
R. G. Kleva, P. N. Guzdar (IREAP, University of Maryland, College Park, MD)
[FP1.082] An eigenvalue formulation for the feedback stabilization of resistive wall modes in a toroidal geometry
Hogun Jhang (Korea Basic Science Institute), Sheung-hoe Ku (Korea Advanced Institute of Science and Technology), Jin-Yong Kim (Korea Basic Science Institute)
[FP1.083] Two-step control of wall mode and the monodromy matrix
Henri Tasso (Max-Planck-Institut fuer Plasmaphysik, 85748 Garching, Germany), George N. Throumoulopoulos (Theoretical Physics Division, University of Ioannina, GR 45110 Ioannina, Greece)
[FP1.084] Feedback and Control of Linear and Nonlinear Global MHD Modes in Rotating Plasmas
J. M. Finn, L. Chacon (LANL)
[FP1.085] Theoretical simulation of the feedback of the resistive wall mode
M. S. Chance (Princeton Plasma Physics Laboratory), M. S. Chu (General Atomics), M. Okabayashi (Princeton Plasma Physics Laboratory)
[FP1.086] Dynamic Responses of Tokamak Plasmas Induced by Externally Applied Rotating Helical Magnetic Field in Dynamic Ergodic Divertor
Yusuke Kikuchi (Graduate School of Engineering, Nagoya University), Yoshihiko Uesugi (CIRSE, Nagoya University), Shuichi Takamura (Graduate School of Engineering, Nagoya University), Viatcheslav Budaev (Kurchatov Institute)
[FP1.087] Two-Dimensional MHD Simulations of Tokamak Plasmas with Poloidal Flow
L. Guazzotto, R. Betti (Laboratory for Laser Energetics, U. of Rochester)
[FP1.088] Magnetic Island Induced Bootstrap Current and Its Implications
K. C. Shaing (University of Wisconsin)
[FP1.089] Nonlinear evolution of shear-localized ideal interchange instability
Sangeeta Gupta, J. D. Callen, C. C. Hegna (University of Wisconsin, Madison, Wisconsin 53706-1687)
[FP1.090] Hybrid MHD Ballooning Instabilities?
J.D. Callen, C.C. Hegna (Univ. of Wisconsin, Madison, WI 53706-1687)
[FP1.091] On the Dynamics of Taylor Relaxation
P.H. Diamond, M. Malkov (University of California, San Diego, La Jolla, CA 92093-0319 USA)
[FP1.092] MHD dynamics of relaxed plasmas sustained by Oscillating Field Current Drive
Fatima Ebrahimi, S. C. Prager, J. C. Wright, J. S. Sarff (University of Wisconsin-Madison)
[FP1.093] Magnetic Structures within Flowing Plasmas
Zhehui Wang (Los Alamos National Lab.)
[FP1.094] Investigation of the initial inductive startup in a tokamak plasma
Kim Jayhyun (Korea Advanced Institute of Science and Technology), Choe W. (KAIST)
[FP1.095] Free-boundary 1 amp; 1/2D Simulation of Disruptions in ITER-FEAT.
L.L. LoDestro, L.D. Pearlstein, D.A. Humphreys (GA.)
[FP1.096] Dynamics of toroidally coupled magnetic perturbations and seed magnetic island formation in tokamak plasmas
C. C. Hegna, J. D. Callen (University of Wisconsin)
[FP1.097] Dusty and Non-Neutral Plasmas
[FP1.098] ROLE AND PROPERTIES OF FORMED SOLITARY ELECTRIC FIELD IN DUSTY PLASMA FLOW WITH FULLERENES IN SOURCE OF NANOTUBES
Sergey V. Barchuk, Vladimir I. Lapshin, Vasyl I. Maslov, Ivan N. Onishchenko, Vitalij N. Tretyakov (NSC Kharkov Institute of Physics and Technoogy, 61108, Kharkov, Ukraine, e-mail: vmaslov@kipt.kharkov.ua)
[FP1.099] 3D Structural and dynamical measurement of a complex plasma crystalization
Dirk David Goldbeck, Rick A. Quinn, Gregor E. Morfill (MPE Garching, Germany), Siegfried Boseck (University of Bremen, Germany)
[FP1.100] A Nonlinear Theory of Void Formation in Colloidal Plasmas
K. Avinash, A. Bhattacharjee, S. Hu (The University of Iowa)
[FP1.101] Dust grain charging and levitation in a weakly collisional DC sheath
A. A. Sickafoose, J. Colwell, M. Horanyi, S. Robertson (University of Colorado, Boulder, CO)
[FP1.102] Nonlinear compressional waves in a 2D dusty plasma crystal: Theory
J. Goree, K. Avinash, B. Liu, V. Nosenko (Dept. of Physics and Astronomy, The Univ. of Iowa)
[FP1.103] Nonlinear compressional waves in a 2D dusty plasma crystal: Experiment
V. Nosenko, K. Avinash, B. Liu, J. Goree (Dept. of Physics amp; Astronomy, The Univ. of Iowa)
[FP1.104] Nonlinear compressional waves in a 2D dusty plasma crystal: Simulation
B. Liu, K. Avinash, J. Goree, V. Nosenko (Dept. of Physics amp; Astronomy, The Univ. of Iowa)
[FP1.105] Phase Transition in Dusty Plasmas: A Microphysical Description ^*
Gurudas Ganguli, Glenn Joyce, Martin Lampe (Plasma Physics Division, Naval Research Laboratory)
[FP1.106] Measurement of charged aerosol particles in the mesosphere by a rocket-borne probe
Byron Smiley, Mihaly Horanyi, Scott Robertson (University of Colorado, Boulder CO)
[FP1.107] Interaction of Small Bodies with the Atmosphere
Gian Luca Delzanno, Giovanni Lapenta (LANL), Marlene Rosenberg (UCSD)
[FP1.108] Controlled interactions of microparticle clouds in a dc glow discharge dusty plasma
Jr. Thomas (Auburn University), Brendan McGeehan (West Virginia University)
[FP1.109] Probe induced voids in a dusty plasma
R. L. Merlino (Department of Physics and Astronomy, The University of Iowa), Jr. Thomas (Department of Physics, Auburn University), K. Avinash, A. Bhattacharjee (Department of Physics and Astronomy, The University of Iowa)
[FP1.110] Expansion Rate Scaling and Diagnostic Development on the Electron Diffusion Gauge Experiment.
Kyle Morrison, Stephen Paul, Ronald Davidson (Princeton Plasma Physics Laboratory)
[FP1.111] Cryogenic Positron Plasma in a 5 Tesla Field
P. Schmidt, J. R. Danielson, J. P. Sullivan, C. M. Surko (University of California San Diego)
[FP1.112] Design of a High-Capacity Penning-Malmberg Trap for Positrons.
C. M. Surko (University of California San Diego), R. G. Greaves (First Point Scientific, Inc.)
[FP1.113] Two-Stream Interactions in Guiding-Center Plasmas for Antihydrogen Recombination Schemes
Ronald Stowell, Ronald Davidson (Princeton Plasma Physics Laboratory)
[FP1.114] Progress on new temperature measurements and excitation of shear modes in Penning trap ion crystals
M. Jensen, J.J. Bollinger, J.M. Kriesel (NIST, Boulder, CO 80305)
[FP1.115] Isolating Diffusive Effects in Asymmetry-Induced Transport
D.L. Eggleston, F.O. Rebassoo (Occidental College)
[FP1.116] Numerical Simulation of Ultracold Plasmas.
S.G. Kuzmin, T.M. O'Neil (UCSD)
[FP1.117] Shear-Limited Test Particle Transport in Two-Dimensional Plasmas.
F. Anderegg, C.F. Driscoll, D.H.E. Dubin, T.M. O'Neil (UCSD)
[FP1.118] Shear-Reduction of Collisional Transport in a 2D Point Vortex Gas/Plasma.
D.H.E. Dubin (UCSD)
[FP1.119] A Numerical Study of the Influence of Dynamics on 2D Turbulent Relaxation.
S.C. Walker, D.H.E. Dubin (UCSD)
[FP1.120] Observation of Diocotron Wave Echoes in a Pure Electron Plasma.
J.H. Yu, C.F. Driscoll (UCSD)
[FP1.121] A Theory of Trapped-Particle Asymmetry Mode Damping.
T.J. Hilsabeck, T.M. O'Neil (UCSD)
[FP1.122] Measurement of Trapped-Particle Mode Damping in Electron Plasmas.
A.A. Kabantsev, C.F. Driscoll (UCSD)
[FP1.123] Resonant and Non-Resonant Thermal Fluctuations in Pure Electron Plasmas.
N. Shiga, F. Anderegg, D.H.E. Dubin, C.F. Driscoll (UCSD), R.W. Gould (Caltech)
[FP1.124] Simulations of Damping of Trapped Particle Asymmetry Modes in Non-Neutral Plasma Columns
Grant W. Mason, Ross L. Spencer (Brigham Young University)
[FP1.125] A comparison of experimentally-determined plasma oscillation frequencies with simulation.
Bryan G. Peterson, Grant W. Hart, Ross L. Spencer (Brigham Young University)
[FP1.126] An analytic model for the spectrum of the noise temperature diagnostic
Grant W. Hart, Bryan G. Peterson, M. Takeshi Nakata (Brigham Young University)
[FP1.127] Ion Trapping in the Virtual Cathode of PFX-I
Martin Schauer, Daniel Barnes (Los Alamos National Laboratory)
[FP1.128] The Columbia Non-neutral Torus and the Physics of non-neutral plasmas confined on magnetic surfaces.
T. Sunn Pedersen, J. P. Kremer, A. H. Boozer, R. Schmitt (Columbia University)
[FP1.129] Status of the Columbia Non-neutral Torus
J. P. Kremer, T. Sunn Pedersen (Columbia University), N. Pomphrey, W. Reiersen, A. Brooks, F. Dahlgren (PPPL)
[FP1.130] Thermal Fluctuations in Pure Electron Plasmas
Roy W. Gould (California Institute of Technology)
[FP1.131] Experimental and Theoretical Studies of Electrostatic Confinement
Jaeyoung Park, Richard Nebel (Los Alamos National Laboratory)
[FP1.132] Flat-top conundrum
Joel Fajans, Thomas Pasquini (U.C. Berkeley)
[FP1.133] Ion Resonance Instability in a Double Well Trap
Thomas Pasquini, Joel Fajans (U.C. Berkeley)
[FP1.134] Electron Injection into Malberg-Penning Plasma Traps
Vladimir V. Gorgadze, Thomas A. Pasquini, Jonathan S. Wurtele, Joel Fajans (Physics Department, University of California, Berkeley)
[FP1.135] Buffer gas cooling of pure-electron plasmas
William Bertsche, Joel Fajans (U. C. Berkeley)
[FP1.136] Three-dimensional PIC codes for non-neutral plasmas.
Nathan Hallquist, Joel Fajans, John Verboncoeur, Jonathan Wurtele (U.C. Berkeley)
[FP1.137] Nonlinear PIC Simulations for Nonneutral Plasmas
Giovanni Lapenta, Gian Luca Delzanno, John M. Finn (LANL)
[FP1.138] Electron diffusion in the annular Penning trap
Scott Robertson, Qudsia Quraishi (University of Colorado, Boulder, CO), Bob Walch (Univ. of Northern Colorado, Greeley, CO)
[FP1.139] Limitations on Confinement of a Toroidal Electron Plasma due to Field Asymmetries and the Presence of Neutrals
M. R. Stoneking, R. T. Peterson, M. A. Growdon, D. J. Thuecks (Lawrence University, Appleton, WI 54911)
[FP1.140] Finite length diocotron mode in ELTRAP
R. Pozzoli, G. Bettega, F. Cavaliere, F. De Luca, M. Rome', S. Sossi (INFM, Dip. Fisica Universita' di Milano, Italy), M. Cavenago (INFN Laboratori Nazionali di Legnaro, Italy), M. Amoretti (INFN Sez. Genova, Italy)
[FP1.141] Longitudinal cooling of a strongly magnetized electron plasma
Jinhyung Lee, John Cary (CIPS and Department of Physics, University of Colorado at Boulder)
[FP1.142] ICF Technologies
[FP1.143] Ultrafast X-ray Difraction for Measurements of Structural Dynamics in Shocked Metals
Jonathan B Workman, Paul Keiter, George A Kyrala, Jeff P Roberts, Antoinette J Taylor, II Funk (Los Alamos National Lab)
[FP1.144] Two-dimensional ablation density measurement with micrometer resolution Fresnel phase zone plate
Y Tamari, H Azechi, M Nishikino, T Sakaiya, S Fujioka, H Shiraga, M Nakai, K Shigemori (Institute of Laser Engineering, Osaka University)
[FP1.145] Kinetics calculations for K-shell Kr multi-keV x-ray production experiments at OMEGA
K. B. Fournier, C. A. Back, M. C. Miller, L. J. Suter, H.-K. Chung
[FP1.146] Non-LTE Kinetics modeling of krypton ions : calculations of radiative cooling coefficients
Hyun-Kyung Chung, Kevin B. Fournier, Richard W. Lee (Lawrence Livermore National Laboratory, Livermore CA)
[FP1.147] An Anomaly in the Inglis-Teller Limits of the C VI Lyman and Balmer Series in Laser-Produced Plasmas
R. ELTON, E. IGLESIAS, H. GRIEM (U. of Maryland), J. WEAVER (NRL), G. PIEN (U. of Rochester), R. MANCINI (U. of Nevada, Reno)
[FP1.148] Modeling of x-ray detection using microchannel plates
K.E. Korreck, R.P. Drake, P. Susalla, E.C. Harding (Univ. of Michigan), J. Weaver (Naval Research Laboratory)
[FP1.149] Spatial structure data of ultra-thin Au films for instability modeling
Edmund Hsieh, Brian Motta (Affiliation), Tom Walsh (Schafer Corporation, 303 Lindbergh Ave., Livermore, CA 94551), John Gardner (Naval Research Lab., 4555 Overlook Ave., SW, Wash. DC, 20375), Donald Wall (General Atomics, P.O.Box 85608, San Diego, CA 92186), Schafer Corporation Collaboration, Naval Research Lab Collaboration, General Atomics Collaboration
[FP1.150] Planar Target Fabrication in Support of HEDP Research
T. Walsh, S. Carter, P. Collins, S. Faulk, S. Gross, E. Hsieh, D. Mathews, B. Motta, D. Schroen, J. Varadarajan, K. Youngblood (Schafer Corporation, Livermore, CA), Y. Aglitskiy (Science Applications International Corporation, McLean, VA), A. N. Mostovych, A. L. Velikovich (Plasma Physics Division, Naval Research Laboratory, Washington, D.C.)
[FP1.151] Modeling of indirect laser-driven ICF implosions and experimentally observable spectral properties.
I.E. Golovkin, J.J. MacFarlane, P.R. Woodruff (Prism Computational Sciences), L.A. Welser, D.L. McCrorey, R.C. Mancini (University of Nevada, Reno), J.A. Koch (Lawrence Livermore National Laboratory)
[FP1.152] Effects of Line Shifts and the Ion Quadrupole Contribution on Spectral Line Assymetries
Mark A. Gunderson, Norman D. Delamater, David P. Kilcrease (Los Alamos National Laboratory, Los Alamos, NM 87501), Donald A. Haynes Jr. (Fusion Technology Institute, University of Wisconsin, Madison, WI 53706)
[FP1.153] Improving Numerical Efficiency in Three-dimensional ICF Target Simulations
David Fyfe, John Gardner (Laboratory for Computational Physics, Naval Research Laboratory), Andrew Schmitt, Steven Zalesak (Plasma Physics Division, Naval Research Laboratory), Gopal Patnaik (Laboratory for Computational Physics, Naval Research Laboratory)
[FP1.154] The VNIIEF/LANL Collaboration: Ten years of scientific benefit to the Russian Federation and the United States
I. R. Lindemuth, C. M. Fowler, R. E. Reinovsky (Los Alamos National Laboratory), V. K. Chernyshev, V. N. Mokhov (Russian Institute of Experimental Physics)
[FP1.155] Energy Transport in a Wall-Confined Inverse Z-Pinch
Volodymyr Makhin, Richard Siemon, Bruno Bauer, Radu Presura, Vladimir Sotnikov (University of Nevada, Reno NV), Irvin Lindemuth, Ronald Kirkpatrick, Peter Sheehey (Los Alamos National Laboratory, Los Alamos NM)
[FP1.156] Near-Field Nonuniformities in Angularly Multiplexed KrF Lasers
R. H. Lehmberg, Y. Chan (Naval Research Laboratory, Washington, DC 20375)
[FP1.157] Amplifier Modeling and Scaling for the Electra krF Laser
J.L. Giuliani, P. Kepple, R. Lehmberg, J. Sethian (Plasma Physics Division, Naval Research Laboratory), G. Petrov (Berkeley Research Associates), M.F. Wolford (Science Applications International)
[FP1.158] Efficient Energy Deposition for an Electron Beam Pumped KrF Laser
F. Hegeler (Commonwealth Technology, Inc., Alexandria, VA 22315), M. C. Myers, M. Friedman, J. D. Sethian (Naval Research Laboratory, Plasma Physics Division, Washington, DC 20375), S. B. Swanekamp (TITAN/JAYCOR, McLean, VA 22102), D. V. Rose, D. R. Welch (Mission Research Corporation, Albuquerque, NM 87110)
[FP1.159] Space-variant phase/polarization of ultra-short-pulse laser, I - Generation of intense optical vortex and intense longitudinal electric field
Miyaji Godai, Miyanaga Noriaki, Sueda Keiichi, Ohbayashi Ken (Institute of Laser Engineering, Osaka University)
[FP1.160] Space-variant phase/polarization of ultra-short-pulse laser, II - Preliminary observation of interaction with plasma
Noriaki Miyanaga, Godai Miyaji, Ken Ohbayashi, Keiichi Sueda, Kenji Saito, Shuji Sakabe, Shin-ichiro Okihara, Katsunobu Nishihara (Institute of Laser Engineering, Osaka University)
[FP1.161] Calculation of the Response of Inertial Fusion Energy Materials to X-ray and Ion Irradiation on Z and RHEPP
Robert R. Peterson (Los Alamos National Laboratory), Igor E. Golovkin (Prism Computional Sciences), Timothy J. Renk, Tina J. Tanaka, Gregory A. Rochau, Craig L. Olson (Sandia National Laboratories-Albuquerque)
[FP1.162] IFE Chamber Wall Materials Response to Pulsed X-rays on Z and Ions on RHEPP* **
T. J. Renk, T. J. Tanaka, C. L. Olson, G. A. Rochau (Sandia National Laboratories), R. R. Peterson (Los Alamos National Laboratory), I. E. Golovkin (Prism Computational Sciences), T. R. Knowles (Energy Science Laboratories, Inc.)
[FP1.163] Response of Dry Wall Chamber Designs to the Output Spectrum from a Directly Driven Laser IFE Target
Donald Haynes, Robert Peterson (University of Wisconsin), High Average Power Laser (HAPL) Team
[FP1.164] On Afterglow Plasma Parameter Evolution and Heat Flux to the Target*
Boris Frolov, Sergei Krasheninnikov, Alexander Pigarov (University of California, San Diego)
[FP1.165] Investigation of plasma development in magnetically insulated transmission lines
Radu Presura (Nevada Terawatt Facility, University of Nevada, Reno, NV 89506), Bruno Bauer, Stephan Fuelling, Jack Glassman, Vladimir Ivanov, Nathalie Le Galloudec, Volodymyr Makhin, Vladimir Sotnikov, Stephen Batie, Alexey Astanovitskiy, Harold Faretto, Bruno Le Galloudec, Andrew Oxner, Milena Angelova, Rick Glaspy, Sean Keely, Sonrisa Rogowski, Jason Sturz, Zachary Wilkes
[FP1.166] Consideration on Cathode Structure in Mather-type Plasma Focus Devices
Mehrdad A.M. Kashani, Tetsu Miyamoto (Plasma Lab.,College of Science and Technology, Nihon University, Kanda-Surugadai, Chiyoda-Ku, Tokyo101, Japan)
[FP1.167] Study of the neutron pulse regularity of a small dense plasma focus device by time of flight measurements
Fermín Castillo, Julio Herrera, José Rangel (Instituto de Ciencias Nucleares, UNAM)